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CAC:MF7573, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B (Open) |
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Category:Code Relief or Alternative
MONTHYEARML21253A0102021-10-15015 October 2021 Revised Relief Request RR-A39 for the Fourth 10-Year Inservice Inspection Interval NRC-20-0054, Submittal of Revised Relief Request RR-A39 for the Fourth Ten-Year Inservice Inspection Interval2020-12-30030 December 2020 Submittal of Revised Relief Request RR-A39 for the Fourth Ten-Year Inservice Inspection Interval ML20169A6522020-07-0808 July 2020 Revised Valve Relief Request VRR-004 for the Inservice Testing Program Fourth 10-Year Interval NRC-20-0030, Submittal of Relief Request RR-A42 for Inservice Inspection Impracticality During the Third Ten-Year Inservi?E Inspection Interval2020-04-30030 April 2020 Submittal of Relief Request RR-A42 for Inservice Inspection Impracticality During the Third Ten-Year Inservi?E Inspection Interval ML20014E7312020-01-24024 January 2020 Issuance of Relief Proposed Alternative Request Nos. VRR-002, VRR-003, VRR-006, VRR-008, and VRR-009 Associated with Fourth Ten Year Interval Inservice Testing of Various Valves (EPID L-2019-LLR-0048, EPID L-2019-LLR-0049 ML19336A0062020-01-10010 January 2020 Issuance of Relief Proposed Alternative Request Nos. PRR-001 and PRR-004 Associated with Fourth Ten Year Interval Pump Inservice Testing Program (EPID L-2019-LLR-0038 and EPID L-2019-LLR-0041) ML19171A3572019-06-27027 June 2019 Relief from the Requirements of the ASME Code PRR-002 and PRR-003 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-19-0017, Submittal of the Snubber Program Relief Request RR-S1 for the Fourth 10-Year Interval2019-02-28028 February 2019 Submittal of the Snubber Program Relief Request RR-S1 for the Fourth 10-Year Interval ML16357A2802017-01-18018 January 2017 Relief from the Requirements of the ASME Code ML16230A5082016-09-23023 September 2016 Revised Relief Request No. PRR-007 for the Inservice Testing Program Third10-year Interval (CAC No. Mf7573) ML14176A9292014-07-16016 July 2014 Alternative Request PVRR-001 Concerning the Third 10-Year Inservice Testing Program ML1027201602010-10-0505 October 2010 Relief Request No. PRR-09, Relief from Fixed Reference Value Testing for the Third 10-Year Inservice Testing Program Interval ML0311206062003-06-0303 June 2003 Second 10-Year Inservice Inspection Requests for Code Relief RR-A33 and RR-A34 2021-10-15
[Table view] Category:Letter
MONTHYEARIR 05000341/20240122024-11-0101 November 2024 Commercial Grade Dedication Inspection Report 05000341/2024012 IR 05000341/20245012024-10-0808 October 2024 – Emergency Preparedness Inspection Report 05000341/2024501 ML24276A2032024-10-0303 October 2024 FEMA Level 1 Finding Transmittal Letter ML24268A0992024-10-0101 October 2024 Power Plant – Audit Summary for License Amendment Request and Regulatory Exemptions for a Risk Informed Approach to Address ECCS Strainer Performance IR 05000341/20240132024-09-30030 September 2024 Phase 2 Post Approval License Renewal Report 05000341/2024013 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24257A1652024-09-13013 September 2024 FEMA Region 5 Fermi 2 Nuclear Power Plant Level 1 Finding September 2024 ML24254A3562024-09-0909 September 2024 FEMA Level 1 Finding for Fermi 2024 Biennial Exercise ML24240A3532024-08-27027 August 2024 Inservice Testing (IST) Program for the Fourth 10-Year Inspection Interval Update IR 05000341/20240052024-08-22022 August 2024 Updated Inspection Plan for Fermi Power Plant, Unit 2 (Report 05000341/2024005) IR 05000341/20244042024-08-21021 August 2024 Public-Fermi Power Plant, Unit 2 - Material Control and Accounting Program Inspection Report 05000341/2024404 IR 05000341/20240022024-08-14014 August 2024 Integrated Inspection Report 05000341/2024002 ML24199A2182024-07-25025 July 2024 Enrico Fermi Atomic Power Plant, Unit 1 - NRC Position on Continuation of Possession-Only License No. DPR-9 Past the Current Expiration Date (Docket No. 50-016) ML24169A4092024-07-18018 July 2024 Relief Request RR-A25, Alternative to Reactor Vessel Circumferential Shell Weld Examination IR 05000341/20243022024-07-0909 July 2024 NRC Initial License Reexamination Report 05000341/2024302 ML24173A1012024-06-14014 June 2024 Retake Exam Post-Exam Cover Letter & Comments ML24155A0852024-06-11011 June 2024 Operator Licensing Reexamination Approval Letter - Fermi Power Plant, June 2024 ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities IR 05000341/20244022024-05-30030 May 2024 Security Baseline Inspection Report 05000341/2024402 ML24143A1852024-05-29029 May 2024 – Regulatory Audit in Support of LAR to Adopt TSTF-505, Rev. 2, TSTF-439, Rev. 2, and TSTF-591, Rev. 0 ML24141A2072024-05-20020 May 2024 Plant—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 05000341/LER-2024-002, Primary Containment Isolation Valve Declared Inoperable for a Period Prohibited by Technical Specifications2024-05-16016 May 2024 Primary Containment Isolation Valve Declared Inoperable for a Period Prohibited by Technical Specifications 05000341/LER-2024-001, Automatic RPS Scram on High RPV Pressure While Attempting to Lower Generator Output During RF-222024-05-15015 May 2024 Automatic RPS Scram on High RPV Pressure While Attempting to Lower Generator Output During RF-22 IR 05000341/20240102024-05-0606 May 2024 NRC Inspection Report 05000341/2024010 ML24052A2772024-04-30030 April 2024 Issuance of Amendment No. 229 Regarding Revision of Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 IR 05000341/20240012024-04-30030 April 2024 Integrated Inspection Report 05000341/2024001 ML24107B1372024-04-18018 April 2024 Confirmation of Initial License Reexamination June 2024 ML24101A3732024-04-11011 April 2024 Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000341/2024012 ML24100A8422024-04-0909 April 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection: Inspection Report 05000341/2024013 IR 05000341/20234022024-04-0808 April 2024 Reissue - Fermi Power Plant, Unit 2 - Cyber Security Inspection Report 05000341/2023402 (Public) ML24088A2162024-04-0404 April 2024 Change in Estimated Review Schedule and Level of Effort for License Amendment Request for Risk Informed Approach to ECCS Strainer Performance ML24086A5732024-04-0101 April 2024 Response to Disputed Non-Cited Violation Documents in Fermi Power Plant, Unit 2 - Cyber Security Inspection Report 05000341/2023402-01 Withdrawal of Non-Cited Violation (Public) IR 05000341/20243012024-04-0101 April 2024 NRC Initial License Examination Report 05000341/2024301 IR 05000341/20244012024-03-22022 March 2024 – Security Baseline Inspection Report 05000341/2024401 (Public) IR 05000341/20240112024-03-0808 March 2024 Nbsp;Safety Conscious Work Environment Issue of Concern Follow-up Inspection Report 05000341/2024011 ML24002B1812024-03-0404 March 2024 Issuance of Amendment No. 228 Regarding Revision of Non-Conservative Technical Specification 3.4.5, RCS Pressure Isolation Valve (PIV) Leakage IR 05000341/20230062024-02-28028 February 2024 Annual Assessment Letter for Fermi Power Plant, Unit 2 (Report 05000341/2023006) ML24019A1842024-02-16016 February 2024 Exemption from Select Requirements of 10 CFR Part 73 Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24045A1602024-02-14014 February 2024 Operator Licensing Examination Approval - Fermi Power Plant, February 2024 IR 05000341/20230042024-02-0505 February 2024 Integrated Inspection Report 05000341/2023004 IR 05000341/20230102023-12-0808 December 2023 Nbsp;Biennial Problem Identification and Resolution Inspection Report 05000341/2023010 ML23341A1852023-12-0808 December 2023 Acknowledgement of Response to NRC Inspection Report 05000341/2023402 and Disputed Non-Cited Violation ML23310A1492023-12-0808 December 2023 Issuance of Amendment No. 227 Regarding Revision of Technical Specification 3.8.1, AC Sources - Operating, Emergency Diesel Generator Voltage and Frequency Surveillance Requirements ML23334A1902023-12-0101 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000341/2024010 ML23335A0062023-12-0101 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000341/2024002 IR 05000016/20230012023-12-0101 December 2023 NRC Inspection Report No. 050-00016/2023-001 (Drss) - Enrico Fermi Atomic Power Plant, Unit 1 IR 05000341/20230032023-11-0707 November 2023 Integrated Inspection Report 05000341/2023003 and 07200071/2023001 ML23297A0512023-10-30030 October 2023 Issuance of Amendment No. 226 Regarding Revision of Technical Specifications 3.8.1, AC Sources - Operating (Exigent Circumstances) ML23311A3482023-10-20020 October 2023 DTE Electric Company (DTE) - Submittal of the Renewed Fermi 3 Michigan Department of Environmental, Great Lakes, and Energy (EGLE) National Pollutant Discharge Elimination System (NPDES) Permit No. MI0058892 ML23272A1552023-10-10010 October 2023 – Letter to Licensee and Federal Register Notification of Amendment to Renewed Facility Operating License and Proposed No Significant Hazards Consideration Determination (Exigent Circumstances) (EPID L-2023-LLA-0134) (Letter) 2024-09-09
[Table view] Category:Safety Evaluation
MONTHYEARML24169A4092024-07-18018 July 2024 Relief Request RR-A25, Alternative to Reactor Vessel Circumferential Shell Weld Examination ML24052A2772024-04-30030 April 2024 Issuance of Amendment No. 229 Regarding Revision of Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 ML24002B1812024-03-0404 March 2024 Issuance of Amendment No. 228 Regarding Revision of Non-Conservative Technical Specification 3.4.5, RCS Pressure Isolation Valve (PIV) Leakage ML23310A1492023-12-0808 December 2023 Issuance of Amendment No. 227 Regarding Revision of Technical Specification 3.8.1, AC Sources - Operating, Emergency Diesel Generator Voltage and Frequency Surveillance Requirements ML23297A0512023-10-30030 October 2023 Issuance of Amendment No. 226 Regarding Revision of Technical Specifications 3.8.1, AC Sources - Operating (Exigent Circumstances) ML23243A8852023-09-18018 September 2023 Issuance of Amendment No. 225 Regarding Revision of Technical Specifications 3.7.2, Emergency Equipment Cooling Water, Emergency Equipment Service Water and System and Ultimate Heat Sink (Exigent Circumstances) ML23229A0122023-08-17017 August 2023 Issuance of Amendment No. 224 to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 (Emergency Circumstances) ML23122A2332023-06-26026 June 2023 Issuance of Amendment No. 223 Regarding Revision of Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML21335A2802022-04-0707 April 2022 Issuance of Amendment No. 222 Regarding Revision of Technical Specifications to Remove Obsolete Information, Make Minor Corrections, and Make Several Editorial Changes ML21253A0102021-10-15015 October 2021 Revised Relief Request RR-A39 for the Fourth 10-Year Inservice Inspection Interval ML21147A1672021-06-11011 June 2021 Issuance of Amendment No. 221 Regarding Revision of Technical Specifications to Adopt Technical Specification Task Force Traveler TSTF-563 ML21029A2542021-05-24024 May 2021 Issuance of Amendment No. 220 - Revision to Technical Specifications to Utilize Neutron Absorbing Inserts in Criticality Safety Analysis for Spent Fuel Pool Storage Racks (Non-Proprietary) ML21098A0452021-04-26026 April 2021 Issuance of Amendment No. 219 to Revise Technical Specifications to Adopt TSTF-529 ML21036A0822021-03-12012 March 2021 Relief Request RR-A42 for Inservice Inspection Impracticality During the Third 10-Year Inservice Inspection Interval ML20358A1552021-02-24024 February 2021 Issuance of Amendment No. 218, Revision to Technical Specifications to Change Certain Surveillance Intervals to Accommodate a 24-Month Fuel Cycle ML20294A0352020-12-22022 December 2020 Issuance of Amendment No. 217 - Revision to Technical Specifications for Secondary Containment Surveillance Requirements ML20233A8382020-10-0505 October 2020 Issuance of Amendment No. 216 - Revision to Technical Specification in Response to GE Energy-Nuclear's 10 CFR Part 21 Safety Communication SC05-03 ML20169A6522020-07-0808 July 2020 Revised Valve Relief Request VRR-004 for the Inservice Testing Program Fourth 10-Year Interval ML20034F7842020-02-0707 February 2020 Issuance of Relief Proposed Alternative Requests Nos. 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PRR-001 and PRR-004 Associated with Fourth Ten Year Interval Pump Inservice Testing Program (EPID L-2019-LLR-0038 and EPID L-2019-LLR-0041) ML19288A0732019-12-18018 December 2019 Issuance of Amendment No. 215 Revision to Technical Specification 3.3.5.3 ML19267A0272019-10-0303 October 2019 Proposed Alternative to the Required Examination Associated with Snubbers ML19248C7072019-10-0303 October 2019 Proposed Alternative to the Required Examination Associated with Valves Examination ML19183A4722019-08-19019 August 2019 Relief from the Requirements of the American Society of Mechanical Engineers Code ML19183A0232019-07-31031 July 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 ML19204A2532019-07-20020 July 2019 Relief from the Requirements of the ASME Code ML19171A3572019-06-27027 June 2019 Relief from the Requirements of the ASME Code PRR-002 and PRR-003 ML19169A3152019-06-26026 June 2019 2. - Relief from the Requirements of the ASME Code ML19143A2192019-06-13013 June 2019 Relief from the Requirements of the ASME Code ML18306A4512019-01-0707 January 2019 Issuance of Amendment Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs ML18250A1632018-09-20020 September 2018 Issuance of Amendment No. 212 Elimination of Main Steam Line Radiation Monitor Trip and Isolation Function (CAC No. MG0228; EPID L-2017-LLA-0274) ML18165A2022018-09-13013 September 2018 Issuance of Amendment Regarding the Adoption of TSTF-484, Use of TS 3.10.1 for Scram Time Testing Activities ML18144A0642018-07-17017 July 2018 Issuance of Amendment to Revise Technical Specification Section 3.7.2, Emergency Equipment Cooling Water/Emergency Equipment Service Water System and Ultimate Heat Sink ML18096A6142018-06-0505 June 2018 Relief from the Requirements of the ASME Code ML18108A0222018-05-24024 May 2018 Issuance of Amendment to Revise Technical Specifications 5.5.7 Ventilation Filter Testing Program (Vftp), to Be Consistent with Standard Technical Specifications ML18003A2102018-03-0707 March 2018 Relief from the Requirements of the ASME OM Code (CAC No. MG0119; EPID L-2017-LLR-0082) ML17354B0022018-03-0707 March 2018 Relief from the Requirement of the ASME OM Code (CAC No. MG0070; EPID L-2017-LLR-0079) ML17128A3162017-11-29029 November 2017 Issuance of Amendment to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, Using the Consolidated Line Item Improvement Process ML17076A0272017-04-14014 April 2017 Issuance of Amendment to Revise High Pressure Coolant Injection System and Reactor Core Isolation Cooling System Actuation Instrumentation Technical Specifications ML16351A4602017-03-0909 March 2017 Issuance of Amendment to Extend Containment Leakage Test Frequency ML16357A2802017-01-18018 January 2017 Relief from the Requirements of the ASME Code ML16258A0402016-09-29029 September 2016 Fermi, Unit 2 - Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 (CAC Nos. MF0770 and MF0771) ML16230A5082016-09-23023 September 2016 Revised Relief Request No. PRR-007 for the Inservice Testing Program Third10-year Interval (CAC No. Mf7573) ML16069A0062016-04-20020 April 2016 Issuance of Amendment Technical Specifications to Adopt Technical Specifications Task Force - 523, Generic Letter 2008-01, Managing Gas Accumulation ML16054A6372016-04-0505 April 2016 Issuance of Amendment to Revise License Amendment Request to Revise Technical Specification Section 3.5.1, Emergency Core Cooling System - Operating Report ML15233A0842015-09-29029 September 2015 Issuance of Amendment License Amendment Request to Revise the Emergency Action Level Scheme for the Fermi Emergency Plan ML15218A3602015-08-24024 August 2015 Inservice Testing Program Relief Request PRR-012 for Quarterly Test of Core Spray Pumps (Tac No. MF5816) ML15155A5062015-07-29029 July 2015 Request for Use of Mururoa Supplied Air Suits Models MTH2, V4F1 and Blu Suit Systems ML15155B4162015-07-14014 July 2015 Ferm, Uniti 2 - Issuance of Amendment Revise Technical Specifications by Relocating Surveillance Frequencies to Licensee Control in Accordance with Technical Specification Task Force Traveler 425, Revision 3 2024-07-18
[Table view] |
Text
Mr. Paul Fessler Senior Vice President and Chief Nuclear Officer DTE Electric Company Fermi 2 -210 NOC 6400 North Dixie Highway Newport, Ml 48166 September 23, 2016
SUBJECT: FERMI, UNIT NO. 2 -REVISED RELIEF REQUEST NO. PRR-007 FOR THE INSERVICE TESTING PROGRAM THIRD 10-YEAR INTERVAL (CAC NO. MF7573)
Dear Mr. Fessler:
By letter dated April 5, 2016 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML 16097A172), as supplemented by letter dated June 23, 2016 (ADAMS Accession No. ML 16179A 150), DTE Electric Company (DTE, the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the use of an alternative to certain American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) requirements associated with pump inservice testing (IST) program at Fermi 2. Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 O CFR) 50.55a(z)(1 ), the licensee requested to use the proposed alternative on the basis that the alternative provides an acceptable level of quality and safety. The NRC staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that DTE has adequately addressed all of the regulatory requirements set forth in 1 O CFR 50.55a(z)(1) and provides an acceptable level of quality and safety. Therefore, the NRC staff authorizes the use of the alternative request PRR-007, Revision 1, for Fermi for the third 10-year IST program interval, which began on February 17, 2010, and is scheduled to end on February 16, 2020. All other ASME OM Code requirements for which relief was not specifically requested and approved remain applicable. If you have any questions, please contact the NRC Project Manager, Sujata Goetz, at 301-415-8004, or via e-mail at Sujata.Goetz@nrc.gov. Docket No. 50-341
Enclosure:
Safety Evaluation cc w/encls: Distribution via ListServ
Sincerely,Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING REQUEST NO. PRR-007 FOR THE THIRD 10-YEAR INTERVAL INSERVICE TESTING PROGRAM DTE ELECTRIC COMPANY FERMI 2 POWER PLANT DOCKET NO. 50-341 1.0 INTRODUCTION By letter dated April 5, 2016 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML 16097A172), as supplemented by letter dated June 23, 2016 (ADAMS Accession Number ML 16179A 150), DTE Electric Company (DTE, the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC or Commission) for the use of an alternative to certain American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) requirements associated with pump inservice testing (IST) program. Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1 ), the licensee requested to use the proposed alternative on the basis that the alternative provides an acceptable level of quality and safety. 2.0 REGULATORY EVALUATION The regulation at 1 O CFR 50.55a(f), "lnservice Testing Requirements," states, in part, that IST of certain ASME Code Class 1, 2, and 3 pumps and valves be performed in accordance with the specified ASME OM Code and applicable addenda incorporated by reference in the regulations. 1 O CFR 50.55a(z)( 1) states that alternatives to the requirements of paragraph (f) of 1 O CFR 50.55a may be used when authorized by the NRC, if the licensee demonstrates the proposed alternatives would provide an acceptable level of quality and safety. Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request and the Commission to authorize the alternative requested by the licensee. Enclosure
-2 -3.0 TECHNICAL EVALUATION 3.1 Licensee's Request for an Alternative. PRR-007, Revision 1 The applicable ASME Code requirements are as follows:
- ASME OM Code, 2004 Edition, ISTB-3400, "Frequency of lnservice Tests," refers to Table ISTB-3400-1, "lnservice Test Frequency," which specifies that a comprehensive test be performed biennially for Group A and Group B pumps.
- ASME OM Code, 2004 Edition, ISTB-5123, "Comprehensive Test Procedure," specifies the specific requirements for the comprehensive test for centrifugal pumps.
- ASME OM Code, 2004 Edition, ISTB-5223, "Comprehensive Test Procedure," specifies the specific requirements for the comprehensive test for vertical line shaft pumps. ASME OM Code Cases, Code Case OMN-18, "Alternate Testing Requirements for Pumps Tested Quarterly within +/-20% of Design Flow," states, in part, that " ... the Group A test may be performed quarterly within +/-20% of pump design flow rate, with instrumentation meeting the requirements of Table ISTB-3510-1 (Table ISTB-3500-1 in the 1998 Edition through the 2003 Addenda, Table ISTB 4.7.1-1 in the OMc-1994 Addenda through the OMb-1997 Addenda)for the Comprehensive and Preservice Tests, and no comprehensive test is required." The licensee requested to use a modified quarterly Group A test for the IST in lieu of a quarterly Group A and a biennial comprehensive pump test (CPT) for the pumps listed in Table 1, below. The Fermi third 10-year IST program interval began on February 17, 2010, and is scheduled to end on February 16, 2020. The applicable ASME OM Code edition and addenda for the Fermi third 10-year IST program interval is the 2004 Edition, no Addenda.
-3 -Table 1 Pump Description Current ASME Classification Class PumcType E1102C002A RHR Pump A Group A 2 Centrifuaal E1102C002B RHR Pump B Grouo A 2 Centrifuaal E1102C002C RHR Pump C Group A 2 Centrifuaal E1102C002D RHR Pump D Grouo A 2 Centrifuaal E1151C001A RHR Service Water Pump A Group A 3 Vertical Line Shaft E1151C001 B RHR Service Water Pump B Grouo A 3 Vertical Line Shaft E1151C001C RHR Service Water Pump C Group A 3 Vertical Line Shaft E1151C001D RHR Service Water Pump D Grouo A 3 Vertical Line Shaft E4101C001 Hiqh Pressure Coolant Injection Pump Group A 2 Centrifuaal P4400C001A Emeraencv EauiP. Coolina Water Div. 1 Pump Grouo A 3 Centrifuaal P4400C001B Emerqency Equip. Coolinq Water Div. 2 Pump Group A 3 Centrifuqal P4500C002A Emerqencv Eauip. Service Water South Pump Grouo A 3 Vertical Line Shaft P4500C002B Emeraencv Eauip. Service Water North Pump Grouo A 3 Vertical Line Shaft R3001C005 EDG 11 DG Service Water Pump Group A 3 Vertical Line Shaft R3001C006 EDG 12 DG Service Water Pump Grouo A 3 Vertical Line Shaft R3001C007 EOG 13 DG Service Water Pump Group A 3 Vertical Line Shaft R3001C008 EDG 14 DG Service Water Pumo Grouo A 3 Vertical Line Shaft T4100C040 South CCHVAC Chilled Water Pump Group A 3 Centrifuaal T4100C041 North CCHVAC Chilled Water Pump Grouo A 3 Centrifuaal By letter dated April 5, 2016, the licensee stated in part, the following reason for the request: Table ISTB-3400-1 specifies a biennial frequency for the CPT for Group A and Group B pumps. ISTB-5123 describes the specific requirements for performance of CPT for centrifugal pumps. Performance of the biennial CPT on the identified pumps are unnecessary since the existing quarterly pump tests are performed at sufficient flow rate to adequately monitor for pump degradation. Proposed Alternative The licensee proposes that in lieu of the requirements of ISTB-5123 and ISTB-5223, modified Group A tests will be performed quarterly, with instrumentation meeting the instrument accuracy requirements of Table ISTB-3510-1 for the biennial CPT. For the centrifugal pumps, the acceptable range for differential pressure would be 0.90 to 1.06 of the reference value. For the vertical line shaft pumps, the acceptable range for differential pressure would be 0.95 to 1.06 of the reference value, and the alert range would be 0.93 to <0.95 of the reference value. The licensee is proposing this alternative for the pumps listed in Table 1. All of the pumps in Table 1 are currently classified as Group A, and will remain classified as Group A. These acceptable ranges are more conservative than the acceptable ranges in Code Case OMN-18. Section ISTB-3300 requires that the CPT be performed within +/-20 percent of the pump design flow rate. This can be interpreted as either the design accident flow rate, design point, or the best efficiency point, provided that the testing is performed in a region of the pump curve where there is a linear flow to head relationship. This allows the test to properly monitor for pump
-4 -degradation. Table 2 indicates where each pump is tested with respect to flow rate and the pump curve region. Table 2 Pump Description +/-20% Design :t20% Best Linear Region of Accident Flow Efficiency Point Pump Curve Rate Flow Rate E1102C002A RHR Pump A x x E1102C002B RHR Pump B x x E1102C002C RHR Pump C x x E1102C002D RHR Pump D x x E1151C001A RHR Service Water x x Pump A E1151C001B RHR Service Water x x Pump B E1151 C001 C RHR Service Water x x PumpC E1151C001D RHR Service Water x x PumpD E4101C001 High Pressure x x Coolant Injection Pump P4400C001A Emergency Equip. x x Cooling Water Div. 1 Pump P4400C001B Emergency Equip. x x Cooling Water Div. 2 Pump P4500C002A Emergency Equip. x x Service Water South Pump P4500C002B Emergency Equip. x x Service Water North Pump R3001C005 EDG 11 DG Service x x Water Pump R3001C006 EDG 12 DG Service x x Water Pump R3001C007 EDG 13 DG Service x x Water Pump R3001C008 EDG 14 DG Service x x Water Pump T4100C040 South CCHVAC x x Chilled Water Pump T4100C041 North CCHVAC x x Chilled Water Pump The use of ASME OM Code Case OMN-18 allows the performance of a Group A test in lieu of a CPT if the Group A test is conducted at the CPT flow rate using pressure instruments that meet the CPT accuracy requirements. Quarterly Group A pump testing performed at the CPT flow rate is more effective in assessing the pumps' operational readiness, through trending, than a
-5 -Group A test at lower flow rates in conjunction with a biennial CPT. The modified Group A test acceptance criteria (discussed above) will be used for pump IST rather than having to use the CPT criterion for one biennial test. The acceptance criteria for vibration tests would be the same as for Group A tests shown in Tables ISTB-5121-1 and ISTB-5221-1. 3.2 NRC Staff Evaluation The licensee is proposing to use ASME OM Code Case OMN-18, with a modified acceptance criteria, and perform IST for all the pumps listed in Table 1 in accordance with a modified Group A test procedure. The ASME OM Code requires that for Group A pumps, a Group A test is performed every quarter, and a CPT is performed biennially. The Group A test is performed within +/-20 percent of the pump design flow rate (if practicable), the pressure instrument accuracy is +/-2 percent, and the upper limit for the acceptable range for differential pressure is 11 O percent of the reference value. The CPT is performed within +/-20 percent of the pump design flow rate, the pressure instrument accuracy is +/-1/2 percent, and the upper limit of the acceptable range for differential pressure is 103 percent of the reference value. Vibration monitoring is performed during both the Group A test and the CPT. The licensee proposes that for the pumps listed in Table 1, which are classified as Group A, a modified Group A quarterly test be performed every quarter, and the biennial CPT is not required. The modified Group A quarterly test would be performed within +/-20 percent of the pump design accident flow rate for pumps indicated in Table 2. For the pumps indicated in Table 2 as being tested within +/-20 percent of pump best efficiency point flow rate, this is acceptable because the pumps will be operating on a sloped portion of the pump curve where degradation is more detectable. The more accurate pressure instrumentation that is required for a CPT (+/-1/2 percent versus +/-2 percent) will be used. This modified quarterly test would replace the CPT. The acceptable range for differential pressure for the modified Group A quarterly test is more conservative than the range for the Group A quarterly test. The licensee is proposing to perform a modified Group A pump test every quarter and not perform a CPT. The licensee will use a more limiting upper bound of 106 percent for the Acceptable Range for differential pressure in lieu of 110 percent that is required by the OM Code for Group A tests. This proposed upper bound of 106 percent is greater than the upper bound of 103 percent for the biennial CPT. All of the pump tests will be performed with pressure instruments with +/-1/2 percent accuracy. For the pumps that are currently classified as Group A, the elimination of the CPT (with its more limiting differential pressure Acceptable Range upper bound of 103 percent) is compensated for by using more accurate pressure gauges on every quarterly test. This will provide for better trending of pump performance. -Instead of performing seven tests with pressure instruments with +/-2 percent accuracy, and then performing the eighth test with pressure instruments with +/-1/2 percent accuracy, all eight tests will be performed with the same +/-1/2 percent accurate instruments. The proposed alternative would provide reasonable assurance of the operational readiness for the pumps listed in Table 1.
-6 -4.0 CONCLUSION As set forth above, the NRC staff determined that for alternative request PRR-007, Revision 1, for Fermi, the proposed alternative provides an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(1) for request PRR-007, Revision 1, and is in compliance with the ASME OM Code's requirement. Therefore, the NRC staff authorizes the use of the alternative request PRR-007, Revision 1, for Fermi for the third 10-year IST program interval, which began on February 17, 2010, and is scheduled to end on February 16, 2020. All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject requests remain applicable. Principle Contributor: Robert Wolfgang, NRR/DE/EPNB Date of issuance: September 23, 2016