Letter Sequence Approval |
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EPID:L-2021-LLR-0072, CFR 50.55a Requests RP-1, RP-2, RP-3, and RP-4 Regarding Inservice Pump and Valve Testing (Approved, Closed) |
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Category:Code Relief or Alternative
MONTHYEARML22147A1492022-06-0202 June 2022 Relief Request RP-3 Regarding Fuel Oil Transfer Pump Testing ML22136A1092022-05-24024 May 2022 Proposed Alternative Request RP-2 Regarding the Inservice Testing of Certain Pumps ML22118B0382022-05-0505 May 2022 Proposed Alternative Request RP-4 Regarding the Inservice Testing of High-Pressure Injection Pumps ML22082A2532022-03-29029 March 2022 Correction Letter - Issuance of Authorization of Proposed Alternative to Use ASME OM Code Case OMN-27 ML22012A2972022-01-21021 January 2022 Proposed Alternative to Use ASME OM Code Case OMN-27 L-20-256, Request to Use Provision in Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2020-09-28028 September 2020 Request to Use Provision in Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ML18004A1222018-01-22022 January 2018 FENOC-Beaver Valley, Davis-Besse, and Perry - Alternative for the Use of ASME Code Case N-513-4 (CAC Nos. MG0120, MG0121, MG0122, and MG0123; EPID L-2017-LLR-0088) ML16328A1252017-01-23023 January 2017 Relief from the Requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) (TAC No. MF7780 - MF7783) ML14175B5532014-08-28028 August 2014 Correction Letter for Relief Requests RR-A1, RR-B1, RP-1, PR-1A, RP3, RR-A36 ML13210A4672013-08-0101 August 2013 Safety Evaluation for Relief Requests RP-6 and RV-1 ML1113105612011-05-19019 May 2011 Acceptance of Requested Licensing Action Relief Request, Proposed Alternative to System Leakage Test Requirements ML1025715692010-09-20020 September 2010 Nozzle RR ML1002715312010-01-29029 January 2010 Relief Request RR-A32 for the Application of Full Structural Weld Overlays on Dissimilar Metal Welds of Reactor Coolant Piping ML1000805732010-01-21021 January 2010 Unit, Relief Request RR-A33 for the Application of Full Structural Weld Overlays on Dissimilar Metal Welds of Reactor Coolant Piping ML0731905112007-12-20020 December 2007 Request for Alternative RR-A30, Revision 2 to Use Proposed Alternative to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Requirements for Structural Weld Overlays (Tac No. MD4452) ML0732301832007-12-14014 December 2007 Request for Alternative RR-A31 for Pressurizer J-Groove Nozzle Weld Repairs (Tac No. MD5956) ML0624404782006-10-19019 October 2006 Evaluation of Request for Relief from the Requirements of the ASME Code, Full Structural Weld Overlay ML0404201062004-02-26026 February 2004 Relief Request, Inservice Testing for Pressurizer Relief Valve ML0227002792002-09-30030 September 2002 Relief, Third 10-Year Interval Inservice Inspection Program Plan ML0227402332002-09-26026 September 2002 Revision to 10 CFR 50.55a Request RR-B4 Regarding American Society of Mechanical Engineers Boiler and Pressure Vessel Code Inservice Inspection Requirement ML0221906062002-08-0101 August 2002 Firstenergy Nuclear Operating Company 10 CFR 50.55a Requests for Alternatives Pursuant to American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Requirements at the Davis-Besse Nuclear Power Station - Third Ten ML0135301162002-02-20020 February 2002 Inservice Inspection Relief Request No. RR-A22 for the Second 10-Year Inspection Interval 2022-06-02
[Table view] Category:Letter
MONTHYEARML24303A3282024-10-29029 October 2024 Information Request for the Cyber Security Baseline Inspection Identification to Perform Inspection ML24281A0662024-10-0404 October 2024 EN 57363 - MPR Associates, Inc. Report in Accordance with 10 CFR Part 21 on Incomplete Dedication of Contactors Supplied as Basic Components IR 05000346/20244032024-09-27027 September 2024 Security Baseline Inspection Report 05000346/2024403 ML24269A0552024-09-25025 September 2024 Submittal of the Updated Final Safety Analysis Report, Revision 35 05000346/LER-2021-001-01, Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground2024-09-19019 September 2024 Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground ML24134A1522024-09-17017 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter ML24260A2382024-09-16016 September 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML24255A8032024-09-11011 September 2024 Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24249A1602024-09-0505 September 2024 Information Request to Support Upcoming Material Control and Accounting Inspection at Davis-Besse Nuclear Power Station L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000346/20240052024-08-22022 August 2024 Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2024005) L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule IR 05000346/20240022024-08-0101 August 2024 Integrated Inspection Report 05000346/2024002 IR 05000346/20244012024-07-30030 July 2024 Security Baseline Inspection Report 05000346/2024401 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification L-24-032, Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report2024-07-15015 July 2024 Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report L-24-063, License Amendment Request to Remove the Table of Contents from the Technical Specifications2024-07-0808 July 2024 License Amendment Request to Remove the Table of Contents from the Technical Specifications L-24-024, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-19019 June 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-214, Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2024-06-0505 June 2024 Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements L-24-019, Unit No.1 - Report of Facility Changes, Tests, and Experiments2024-05-22022 May 2024 Unit No.1 - Report of Facility Changes, Tests, and Experiments ML24142A3532024-05-21021 May 2024 Station—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-24-072, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 20232024-05-15015 May 2024 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 2023 L-24-111, Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-05-15015 May 2024 Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations L-24-031, Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage2024-05-14014 May 2024 Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage IR 05000346/20240012024-05-0303 May 2024 Integrated Inspection Report 05000346/2024001 L-24-069, Occupational Radiation Exposure Report for Year 20232024-04-30030 April 2024 Occupational Radiation Exposure Report for Year 2023 L-24-018, Submittal of Core Operating Limits Report, Cycle 24, Revision 02024-04-16016 April 2024 Submittal of Core Operating Limits Report, Cycle 24, Revision 0 ML24089A2582024-04-0101 April 2024 Request for Information for the NRC Quuadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000346/2024010 L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage ML24036A3472024-03-0707 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0076 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24057A0752024-03-0101 March 2024 The Associated Independent Spent Fuel Storage Installations ML24057A3362024-02-28028 February 2024 Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006) IR 05000346/20230062024-02-28028 February 2024 Re-Issue Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006) L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024 Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee IR 05000346/20243012024-02-0202 February 2024 NRC Initial License Examination Report 05000346/2024301 IR 05000346/20230042024-01-31031 January 2024 Integrated Inspection Report 05000346/2023004 ML23313A1352024-01-17017 January 2024 Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program ML23353A1192023-12-19019 December 2023 Operator Licensing Examination Approval Davis Besse Nuclear Power Station, January 2024 L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023 Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23338A3172023-12-0606 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001 IR 05000346/20234032023-11-0202 November 2023 Security Baseline Inspection Report 05000346/2023403 ML23293A0612023-11-0101 November 2023 Letter to the Honorable Marcy Kaptur, from Chair Hanson Responds to Letter Regarding Follow Up on Concerns Raised by Union Representatives During the June Visit to the Davis-Besse Nuclear Power Plant ML24045A0322023-10-26026 October 2023 L-23-221 Proposed Exam Submittal Cover Letter L-23-215, Changes to Emergency Plan2023-10-19019 October 2023 Changes to Emergency Plan ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments 2024-09-06
[Table view] Category:Safety Evaluation
MONTHYEARML23313A1352024-01-17017 January 2024 Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program ML23237B4282023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments ML23237B4302023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0000) (Public) ML22269A3582022-11-15015 November 2022 Issuance of Amendment No. 305 Revising the Emergency Plan ML22277A6012022-10-14014 October 2022 Issuance of Amendment No. 304 Revising the Design Basis for the Shield Building Containment Structure ML22210A0102022-09-16016 September 2022 Energy Harbor Fleet- Issuance of Amendments Regarding Adoption of TSTF 554, Revise Reactor Coolant Leakage Requirements ML22147A1492022-06-0202 June 2022 Relief Request RP-3 Regarding Fuel Oil Transfer Pump Testing ML22136A1092022-05-24024 May 2022 Proposed Alternative Request RP-2 Regarding the Inservice Testing of Certain Pumps ML22118B0382022-05-0505 May 2022 Proposed Alternative Request RP-4 Regarding the Inservice Testing of High-Pressure Injection Pumps ML22096A3162022-04-12012 April 2022 Proposed Alternative Request RP-1 Regarding Digital Instrumentation for Inservice Testing ML22082A2532022-03-29029 March 2022 Correction Letter - Issuance of Authorization of Proposed Alternative to Use ASME OM Code Case OMN-27 ML22012A2972022-01-21021 January 2022 Proposed Alternative to Use ASME OM Code Case OMN-27 ML21075A1132021-04-16016 April 2021 Issuance of Amendment Nos. 311, 200, and 302 to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Technical Specifications ML20280A8272020-11-0303 November 2020 Issuance of Amendment No. 301 to Relocate Specific Surveillance Frequencies to a Licensee-Controlled Program ML20279A4402020-10-0808 October 2020 Energy Harbor Fleet-Beaver Valley Power Station; Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant - Request to Use a Provision of a Later Edition of the ASME Engineers Boiler and Pressure Vessel Code, Section XI ML20213C7262020-08-24024 August 2020 Issuance of Amendment No. 300 to Revise the Containment Leakage Rate Testing Program ML19305B1312019-12-0202 December 2019 Firstenergy Nuclear Operating Company - Enclosure 6, Non-Proprietary Safety Evaluation, Direct and Indirect Transfer of Licenses and Draft Conforming Amendments for Beaver Valley Units 1 and 2, Davis-Besse Unit 1, and Perry Unit 1 ML19100A3062019-06-21021 June 2019 Issuance of Amendment No. 298 to Adopt National Fire Protection Association Standard 805 ML19028A0302019-04-11011 April 2019 FENOC - Beaver Valley Power Station, Unit 1 & 2; Davis-Besse Nuclear Power Station Unit 1; and Perry Nuclear Power Plant Unit 1 - Approval of Certified Fuel Handler Training and Retraining Program ML18179A4672018-07-30030 July 2018 FENOC-Beaver Valley Power Station, Unit No. 1 and 2; Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit 1 - Issuance of Amendments Request to Adopt TSTF-529, Clarify Use and Application Rules ML18004A1222018-01-22022 January 2018 FENOC-Beaver Valley, Davis-Besse, and Perry - Alternative for the Use of ASME Code Case N-513-4 (CAC Nos. MG0120, MG0121, MG0122, and MG0123; EPID L-2017-LLR-0088) ML17270A1122017-10-19019 October 2017 Issuance of Amendment Revising Technical Specification Requirements for Ultrasonic Flow Meter Outage Time (CAC No. MF9080; EPID L-2017-LLA-0167) ML17256B1902017-10-12012 October 2017 Time-Limited Aging Analysis for the Reactor Vessel Internals Loss of Ductility at 60 Years ML17081A5092017-05-11011 May 2017 ISFSI, Davis-Besse ISFSI, Perry Nuclear Power Plant, Perry Nuclear Power Plant ISFSI - Issuance of Amendments Re. Application to Revise Technical Specifications to Adopt TSTF-545 Revision 3 ML17017A3402017-01-31031 January 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-051 and EA-12-049 ML16328A1252017-01-23023 January 2017 Relief from the Requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) (TAC No. MF7780 - MF7783) ML16342C9462017-01-12012 January 2017 Issuance of Amendment Revising Emergency Action Level Scheme ML16298A3492017-01-11011 January 2017 Issuance of Amendment Revising Technical Specification Requirements for the Radioactive Effluent Controls Program ML16040A0842016-06-0707 June 2016 FENOC, Beaver Valley Power Station, Unit Nos. 1 and 2; and Davis-Besse Nuclear Power Station, Unit No. 1 - Issuance of Amendments Revision to Technical Specification 5.3.1, Unit Staff Qualifications ML16083A4812016-04-27027 April 2016 Issuance of Amendment Revising Emergency Diesel Generator Minimum Voltage and Frequency Acceptance Criteria ML15302A0752016-03-0808 March 2016 Issuance of Amendment Revising the Completion Date for Milestone 8 of the Cyber Security Plan ML15251A0462015-10-20020 October 2015 Issuance of Amendment Revising Containment Spray Nozzle Surveillance Requirement ML15211A1612015-10-16016 October 2015 FENOC-Beaver Valley Power Station, Unit No. 1; Beaver Valley Power Station ISFSI, Davis-Besse Nuclear Power Station ISFSI, Perry Nuclear Power Plant, Perry Nuclear Power Plant ISFSI Annual Financial Test for a Parent Company Guarantee ML15239B2932015-10-0909 October 2015 Issuance of Amendment Related to Containment Leakage Rate Testing Program ML15182A1912015-07-16016 July 2015 Annual Financial Test for a Parent Company Guarantee Given by Firstenergy Solutions Corporation and Firstenergy Corporation ML14142A2922014-09-12012 September 2014 BVPS, Unit No. 1, BVPS (ISFSI) Davis-Besse Nuclear Power Station ISFSI, Perry Nuclear Power Plant, Unit 1, and Perry Nuclear Power Plant ISFSI - Annual Financial Test for Firstenergy Nuclear Operating Company Parent Company Guarantee (MF374 ML14030A5742014-03-31031 March 2014 Safety Evaluation Concerning Comprehensive Pump Testing Relief Request (TAC No. MF0756) (L-13-067) ML14023A7662014-03-31031 March 2014 Issuance of Amendment Related to Steam Generator Inventory Change (TAC No. MF0536)(L-13-040) ML14030A5922014-02-10010 February 2014 Safety Evaluation for Relief Requests RR-A1 and RR-B1 ML14002A4442014-02-0505 February 2014 Safety Evaluation for Relief Request RP-3 (TAC No. MF0757)(L-13-076) ML14003A2662014-01-27027 January 2014 Davis-besse Nuclear Power Station, Unit 1, Safety Evaluation for Relief Requests RP-1 and RP-1A ML13210A4672013-08-0101 August 2013 Safety Evaluation for Relief Requests RP-6 and RV-1 ML13121A4042013-05-0808 May 2013 Safety Evaluation in Support of Proposed Alternative Regarding Post-Repair Pressure Testing Requirements ML12221A4132012-10-0202 October 2012 Issuance of Amendments Change of the Name of a Owner Licensee to Firstenergy Nuclear Generation, LLC ML12242A4992012-09-11011 September 2012 Safety Evaluation in Support of 10 CFR 50.55a Requests RP-2 and RP-4 Regarding Inservice Pump Testing ML1210706862012-05-11011 May 2012 Safety Evaluation Regarding the Reactor Coolant System Pressure and Temperature Limits Report, Revision 1 ML1208604472012-04-18018 April 2012 Issuance of Amendment Modification of the Special Visual Inspection Requirement of TS 5.5.8 Steam Generator Program ML1207504812012-04-0909 April 2012 Safety Evaluation in Support of 10 CFR 50.55a Request RR-A35, Proposed Alternative to System Leakage Test Requirements ML1124305562011-09-22022 September 2011 Request for Threshold Determination Under 10 CFR 50.80 - Beaver Valley Power Station, Unit Nos. 1 and 2; Davis-Besse Nuclear Power Station, Unit No. 1; and Perry Nuclear Power Plant, Unit No. 1 ML1118903222011-07-11011 July 2011 Review of the Steam Generator Tube Inspections Performed During Refueling Outage No. 16 in 2010 2024-01-17
[Table view] |
Text
June 02, 2022
Mr. Terry J. Brown Site Vice President Energy Harbor Nuclear Corp.
Mail Stop P-DB-3080 5501 North State Route 2 Oak Harbor, OH 43449-9760
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 RELIEF REQUEST RP-3 REGARDING FUEL OIL TRANSFER PUMP TESTING (EPID L-2021-LLR-0072)
Dear Mr. Brown:
By letter dated September 20, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21263A193), as supplemented by letter dated March 21, 2022 (ML22080A214), Energy Harbor Nuclear Corp. (the licensee) submitted relief request RP-3 for the fifth inservice testing (IST) interval at Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse). In accordance with paragraph 50.55a(f)(5)(iii) of Title 10 of the Code of Federal Regulations (10 CFR), the application requests relief from certain IST requirements for two emergency diesel generator (EDG) fuel oil transfer pumps on the basis that compliance with the requirements is impractical. The September 20, 2021, letter also submitted three other requests; however, this letter only pertains to alternative request RP-3.
The requirements applicable to the fifth IST interval at Davis-Besse are in the 2017 Edition of the American Society of Mechanical Engineers (ASME), Operation and Maintenance of Nuclear Power Plants, Division 1, Section IST (OM Code), as incorporated by reference in 10 CFR 50.55a, Codes and standards. The licensee requests relief from the ASME OM Code requirements for periodic testing to measure or det ermine the flow rate, differential pressure, and vibration of the EDG fuel oil transfer pumps at Davis-Besse in lieu of these requirements, the licensee will perform alternative testing and trending to ensure the operational readiness of the pumps.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed relief request RP-3 and concludes, as set forth in the enclosed safety evaluation, that granting relief from the specified ASME OM Code requirements for the periodic testing of the EDG fuel oil transfer pumps at Davis-Besse, pursuant to 10 CFR 50.55a(f)(6)(i), is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. Furthermore, the NRC staff determined that the licensees proposed alternative provides reasonable assurance of the operational readiness of EDG fuel oil transfer pumps. Accordingly, the NRC staff concludes that the licensee has adeq uately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(f)(5)(iii).
T. Brown
Therefore, the NRC staff grants the proposed relief request RP-3 at Davis-Besse for the fifth 10-year IST interval, which is scheduled to begin on September 21, 2022, and end on September 20, 2032.
All other ASME OM Code requirements for which an alternative was not specifically requested and authorized remain applicable.
If you have any questions, please contact Blake Purnell at 301-415-1380 or via e-mail at Blake.Purnell@nrc.gov.
Sincerely,
Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket No. 50-346
Enclosure:
Safety Evaluation
cc: Listserv
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
PROPOSED ALTERNATIVE REQUEST RP-3
ENERGY HARBOR NUCLEAR CORP.
ENERGY HARBOR NUCLEAR GENERATION LLC
DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1
DOCKET NO. 50-346
1.0 INTRODUCTION
By letter dated September 20, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21263A193), as supplemented by letter dated March 21, 2022 (ML22080A214), Energy Harbor Nuclear Corp. (the licensee) submitted relief request RP-3 for the fifth inservice testing (IST) interval at Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse). In accordance with paragraph 50.55a(f)(5)(iii) of Title 10 of the Code of Federal Regulations (10 CFR), the application requests relief from certain IST requirements for two emergency diesel generator (EDG) fuel oil transfer pumps on the basis that compliance with the requirements is impractical. The letter also included three other requests; however, this safety evaluation is only for relief request RP-3.
The requirements applicable to the fifth IST interval at Davis-Besse are in the 2017 Edition of the American Society of Mechanical Engineers (ASME), Operation and Maintenance of Nuclear Power Plants, Division 1, Section IST (OM Code), as incorporated by reference in 10 CFR 50.55a, Codes and standards. The licensee requests relief from the ASME OM Code requirements for periodic testing to measure or det ermine the flow rate, differential pressure, and vibration of the EDG fuel oil transfer pumps at Davis-Besse. In lieu of these requirements, the licensee will perform alternative testing and trending to ensure the operational readiness of the pumps.
2.0 REGULATORY EVALUATION
The regulations in 10 CFR 50.55a(f)(4) state, in part, that throughout the service life of a boiling or pressurized water-cooled nuclear power facility, pumps and valves that are within the scope of the ASME OM Code must meet the IST r equirements (except design and access provisions) set forth in the ASME OM Code and addenda that become effective subsequent to editions and addenda specified in 10 CFR 50.55a(f)(2) and (3) and that are incorporated by reference in 10 CFR 50.55a(a)(1)(iv), to the extent practical within the limitations of design, geometry, and materials of construction of the components.
Enclosure
In accordance with 10 CFR 50.55a(f)(5)(iii), if a licensee has determined that conformance with certain Code requirements is impractical for its facility, the licensee must notify the U.S. Nuclear Regulatory Commission (NRC or Commission) and submit information to support the determination.
The regulations in 10 CFR 50.55a(f)(6)(i) state that the Commission will evaluate determinations under 10 CFR 50.55a(f)(5) that Code requirements are impractical. The Commission may grant such relief and may impose such alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
3.0 TECHNICAL EVALUATION
3.1 Licensees Request
ASME Code Components Affected
The ASME Code Class 3, Group A, EDG fuel oil transfer pump Nos. P195-1 and P195-2.
Applicable Code Edition and Requirements
The applicable ASME OM Code edition for the fifth 10-year IST program interval at Davis-Besse is the 2017 Edition of the ASME OM Code, as incorporated by reference in 10 CFR 50.55a with conditions. The relevant requirements for periodic testing of centrifugal pumps to measure or determine the flow rate, differential pressure, and vibration are in the following ASME OM Code provisions:
Table ISTB-3400-1 requires Group A pump tests to be performed quarterly and a comprehensive pump test to be performed biennially.
Paragraphs ISTB-5121 and ISTB-5123 specify the requirements for the conduct of the Group A pump tests and comprehensive pump tests, respectively.
Table ISTB-5121-1 specifies the acceptance criteria for the Group A and comprehensive pump tests.
=
Reason for Request===
The application states, in part, that:
The EDG fuel oil transfer pumps and motors are submerged inside the EDG fuel oil storage tank and are not accessible for vibration measurements. There are no installed flow instrumentation, pressure instrumentation, valve test connections, or accessible recirculation lines. The pumps transfer diesel fuel oil from the EDG fuel oil storage tanks to the EDG day tanks.
The EDG fuel oil transfer pumps do not have installed instrumentation to measure either flow or discharge pressure. The only possible flow measurement is by measuring EDG day tank volume change over time. Error in measuring this volume is dependent on fuel oil temperature and a limited change in level indication because the EDG day tank has a large upper circular section. Flow rate is dependent upon EDG fuel oil storage tank level and fuel oil viscosity,
which varies with environmental temperature conditions. There are no accessible recirculation pathways nor designed drainage pathways in the pipe line that are used to transfer fuel oil from the EDG fuel oil storage tank to the EDG day tank.
Requested Relief and Proposed Alternative
The licensee requests relief from the following ASME OM Code requirements for periodic testing to measure or determine the flow rate, differential pressure, and vibration of the EDG fuel oil transfer pumps at Davis-Besse:
The Group A pump test requirements in ISTB-5121, subparagraphs (b) through (e).
The comprehensive pump test requirements in ISTB-5123, subparagraphs (b) through (e).
The acceptance criteria in table ISTB-5121-1 for the Group A and comprehensive pump tests.
The Group A and comprehensive pump test frequency requirements in table ISTB-3400-1.
The licensee requested relief for the duration of the fifth 10-year IST program interval at Davis-Besse, which is scheduled to begin on September 21, 2022, and end on September 20, 2032.
The licensee stated that no vibration monitoring of the EDG fuel oil transfer pumps will be performed. As an alternative to these requirements, the licensee stated that it would perform the following:
Fuel oil transfer system functional testing is performed every 92 days as required by Technical Specification Surveillance Requirement 3.8.1.7. This surveillance requirement verifies that the fuel oil transfer system operates to transfer fuel oil from the fuel oil storage tank to the day tank. Periodic operation of the EDGs for testing purposes requires automatic operation of the EDG fuel oil transfer pumps in order to maintain the required level in the EDG day tanks.
Pump flow rate tests are performed each cycle. Fuel oil is added to the EDG fuel oil storage tank, if necessary, to ensure a specified minimum fuel oil level is established above the EDG fuel oil transfer pump prior to testing. The minimum fuel oil level ensures pump suction pressure is consistent for repeatable system flow characteristics.
The pump flow rate is calculated by measuring the change in EDG day tank level over time. An EDG day tank level change of approximately 150 gallons or more is timed to determine flow rate. As described above, consistent EDG fuel oil transfer pump suction pressure is established prior to the test. Based upon these conditions, pump flow rates are repeatable and capable of predicting pump degradation.
The EDG fuel oil transfer pumps are rated at 10 gallons per minute (gpm). A conservative minimum flow value [i.e., 6 gpm], with respect to design basis, will be used in lieu of ASME OM Code Table ISTB-5121-1. This minimum flow value will ensure the EDG fuel oil transfer pumps do not degrade below required design system flow requirements.
Pump flow rates will be trended for degradation. In lieu of alert levels being specified, required actions will be performed if pump flow rate is determined to be outside the acceptable range.
Periodically, the EDG fuel oil storage tanks are drained, cleaned, and filled with fresh oil. The EDG day tanks are also drained, cleaned and inspected. At these times, a long term pump duration test is possible. The transfer pump will be required to continuously pump 1000 gallons of fuel from the EDG fuel oil storage tank to the EDG day tank. Flow rate will be calculated and evaluated for degradation.
3.2 NRC Staff Evaluation
The 2017 Edition of the ASME OM Code requires that the pump flow rate, differential pressure, and vibration to be evaluated against reference values to monitor pump conditions and to allow detection of hydraulic degradation.
The Davis-Besse EDG fuel oil transfer pumps are ASME Code Class 3 components, and the plant was issued a construction permit on March 24, 1971. The regulations in 10 CFR 50.55a(f) do not require ASME Code Class 3 components to have been designed or provided with access to enable the performance of IST for plants issued construction permits between January 1, 1971, and July 1, 1974. The EDG fuel oil transfer pumps are inaccessible for vibration measurements. In addition, there are no installed flow instrumentation, pressure instrumentation, or accessible recirculation lin es to perform the required test measurements.
Therefore, the NRC staff finds that it is impractical to measure or determine the flow rate, differential pressure, and vibration of the EDG fuel oil transfer pumps at Davis-Besse in accordance with the ASME OM Code.
As discussed in section 3.1 of this safety evaluation, the alternative proposed by the licensee includes:
fuel oil transfer system functional testing performed every 92 days, as required by Surveillance Requirement 3.8.1.7; pump flow rate tests each cycle; long term pump duration tests performed when the EDG fuel oil storage tanks are drained and cleaned every 48 months and when the EDG fuel oil day tanks are drained and cleaned every 10 years.
The licensee stated that the pump flow rate tests will be performed under preset and repeatable conditions. The license also stated that the pump flow rates will be evaluated and trended for indications of pump degradation. A minimum flow rate of 6 gpm will be established for test acceptance criteria in lieu of the acceptance criteria in table ISTB-5121-1 for corrective action by the licensee. The March 21, 2022, letter states that there have been no EDG fuel oil transfer pump test failures in the past 10 years. The letter also provided a summary of the results for each EDG fuel oil transfer test performed over the past 10 years that shows the flow rates were all well above the proposed minimum flow rate of 6 gpm for test acceptance. Based on this information, the NRC staff determined that the proposed alternative to the ASME OM Code requirements would provide an adequate means of monitoring the EDG fuel oil transfer pumps for degradation and ensuring the operational readiness of the pumps.
The licensee stated that compliance with the ASME OM Code pump testing requirements would require a major modification of the fuel oil transfer system. The licensee also stated that the Davis-Besse EDG fuel oil transfer pumps have a lower safety significance than other fuel oil transfer systems because of the large capacity of the EDG day tanks and the three diverse methods of replenishing the day tanks during EDG operation. The NRC staff determined that modification of the fuel oil transfer systems at Davis-Besse to allow performance of the pump testing required by the ASME OM Code would be an unnecessary burden on the licensee because of the lower safety significance of the pumps and the proposed alternative means of ensuring the operational readiness of the pumps.
In accordance with 10 CFR 50.55a(f)(6)(i), the NRC staff determined that the licensee has met 10 CFR 50.55a(f)(5)(iii) by demonstrating that conformance with the ASME OM Code requirements for periodic testing to measure or determine the flow rate, differential pressure, and vibration of the EDG fuel oil transfer pumps at Davis-Besse is impractical. The NRC staff also determined that the licensees proposed alternative to test and trend pump performance provides reasonable assurance that the pumps will be operationally ready. Therefore, the NRC staff finds that granting relief from the specif ied ASME OM Code requirements is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the applicable ASME OM Code requirements were imposed on the facility.
4.0 CONCLUSION
As set forth above, the NRC staff determined that granting relief from the specified ASME OM Code requirements for periodic testing of the EDG fuel oil transfer pumps at Davis-Besse, pursuant to 10 CFR 50.55a(f)(6)(i), is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. Furthermore, the NRC staff determined that the licensees proposed alternative provides reasonable assurance of the operational readiness of EDG fuel oil transfer pumps. Accordingly, the NRC staff concludes that the licensee has adeq uately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(f)(5)(iii). Therefore, the NRC staff grants the proposed relief request RP-3 at Davis-Besse for the fifth 10-year IST interval, which is scheduled to begin on September 21, 2022, and end on September 20, 2032.
All other ASME OM Code requirements for which an alternative was not specifically requested and authorized remain applicable.
Principal Contributors: Gurjendra S. Bedi, NRR Blake A. Purnell, NRR
Date: June 02, 2022
ML22147A149 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DEX/EMIB/BC(A)
NAME BPurnell SRohrer ITseng DATE 6/1/22 5/31/22 4/22/22 OFFICE NRR/DORL/LPL3/BC NAME NSalgado (RKuntz for)
DATE 6/2/22