Letter Sequence Approval |
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MONTHYEARML21091A2592021-04-0101 April 2021 and Beaver Valley Power Station, Proposed Alternative to Use ASME OM Code Case OMN-27 Project stage: Request ML21119A2152021-04-28028 April 2021 NRR E-mail Capture - Energy Harbor Fleet, Beaver Valley Units 1 and 2 and DAVIS-BESSE Unit 1 - Acceptance of Relief Request Proposed Alternative to Use ASME OM Code Case OMN-27 Project stage: Acceptance Review ML22012A2972022-01-21021 January 2022 Proposed Alternative to Use ASME OM Code Case OMN-27 Project stage: Other ML22080A2512022-03-18018 March 2022 NRR E-mail Capture - (External_Sender) ASME OM Code Case OMN-27, Alternative Requirements for Testing Category a Valves (Non- Piv/Civ) Project stage: Other ML22082A2532022-03-29029 March 2022 Correction Letter - Issuance of Authorization of Proposed Alternative to Use ASME OM Code Case OMN-27 Project stage: Approval 2022-01-21
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Category:Code Relief or Alternative
MONTHYEARML23249A1842023-09-18018 September 2023 Authorization and Safety Evaluation for Alternative Request No. 2-TYP-4-RV-06 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 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 ML20223A0142020-08-20020 August 2020 Issuance of Relief Request SSR-1, Revision 0, from the Requirements of the ASME Code (EPID L-2020-LLR-0050 (COVID-19)) ML20206K8652020-08-0707 August 2020 Relief Requests 2-TYP-4-RV-06 and 2-TYP-4-RV-07 from the Requirements of the ASME Code (EPID L-2020-LLR-0053 and EPID L-2020-LLR-0054 (COVID-19)) ML20145A0002020-06-0303 June 2020 Relief from the Requirements of the ASME Code for Requests VRR6 and VRR5 (EPID L-2020-LLR-0049 and EPID L-2020-LLR-0051 (COVID-19)) ML20100N3222020-04-0909 April 2020 Verbal Relief for Penetration Evaluation and Hot Leg Nozzles - Delivered 4/9/2020 at 10:00 Am ML20099B2572020-04-0808 April 2020 Verbal Relief Unit 2 CIV ML20098F3012020-04-0707 April 2020 Verbal Relief for Appendix I Safety Relief Valves ML20095J0992020-04-0404 April 2020 Email Beaver Valley Power Station, Unit 2 - Verbal Relief for Snubbers - Delivered 4/4/2020 at 4:00 P.M ML20095J2192020-04-0404 April 2020 Email Beaver Valley Power Station, Unit 2 - Verbal Relief for MOVs - Delivered 4/4/2020 at 4:00 Pm L-20-117, 10 CFR 50.55a Request Number 2-TYP-4-RV-06, Hardship for Hot Leg Nozzle Inspections2020-04-0303 April 2020 10 CFR 50.55a Request Number 2-TYP-4-RV-06, Hardship for Hot Leg Nozzle Inspections L-20-118, CFR 50.55a Request Number SRR-1, Revision 0, Snubber Testing2020-04-0303 April 2020 CFR 50.55a Request Number SRR-1, Revision 0, Snubber Testing L-20-060, CFR 50.55a Request Number: VRR4, Revision 0, Containment Isolation Valve Test Frequency2020-04-0202 April 2020 CFR 50.55a Request Number: VRR4, Revision 0, Containment Isolation Valve Test Frequency L-20-116, CFR 50.55a Request Number VRR6, Revision 0, Motor-Operated Valve Test Frequency2020-04-0101 April 2020 CFR 50.55a Request Number VRR6, Revision 0, Motor-Operated Valve Test Frequency ML20079F8162020-03-26026 March 2020 Relief Requests 1-TYP-4-C2.21-1 and 1-TYP-4-RA-1 Regarding Weld Examination Coverage for the Fourth Inservice Inspection Interval ML19275E2942019-10-16016 October 2019 Issuance of Relief Request Proposed Alternative to Reactor Vessel Nozzle Weld Examination Frequency Requirements in Lieu of Specific ASME Code Requirements L-19-107, Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2019-08-27027 August 2019 Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements ML19051A1082019-02-20020 February 2019 Request Alternative Examination Frequency for Reactor Vessel Nozzle to Safe-End Welds (Request 2-TYP-4-RV-05, Revision 0) ML18227A7332018-08-27027 August 2018 Request for Relief from the Requirements of the ASME Code 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) L-17-317, Request to Extend Certain Reactor Vessel Inspections from 10 to 20 Years (Request 1-TYP-4-BN-01)2017-11-15015 November 2017 Request to Extend Certain Reactor Vessel Inspections from 10 to 20 Years (Request 1-TYP-4-BN-01) L-17-308, 10 CFR 50.55a Request for Alternate Reactor Vessel Nozzle Flaw Depth Sizing Criteria (Request 2-TYP-4-RVSE-2)2017-10-25025 October 2017 10 CFR 50.55a Request for Alternate Reactor Vessel Nozzle Flaw Depth Sizing Criteria (Request 2-TYP-4-RVSE-2) ML17167A0672017-06-26026 June 2017 Requests for Alternatives and Requests for Relief Fourth 10-Year Inservice Test Program Interval (CAC Nos. MF8333-MF8356). Note: Correction Safety Evaluation See ML17255A526 ML17159A4422017-06-26026 June 2017 Requests for Alternatives and Requests for Relief Fifth 10-Year Inservice Testing Program Interval (CAC Nos. MF8332 Through MF8357). Note: Correction Safety Evaluation See ML17255A508 ML17047A6102017-03-0202 March 2017 Relief from the Requirements of the American Society of Mechanical Engineers Code ML17041A1852017-03-0202 March 2017 Relief from the Requirements of the ASME Code ML17048A0042017-03-0202 March 2017 Relief from the Requirements of the ASME Code 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) ML16190A1332016-12-27027 December 2016 Relief from the Requirements of the ASME Code ML16319A0572016-12-0101 December 2016 Acceptance of Requested Licensing Action Relief Request for Proposed Alternative to Perform As-Found Set-Pressure Test ML16257A6212016-11-21021 November 2016 Relief Request BV2-PZR-01, Regarding Alternative to Requirements for Components Connected to the Steam Side of the Pressurizer ML16228A4082016-10-21021 October 2016 Correction to Relief Request 2-TYP-3-RV-04, Revision 0, Regarding Repair Activities for Reactor Vessel Head Penetration Nozzles and Associated J-Groove Welds ML16147A3622016-06-17017 June 2016 Relief Request No. 2-TYP-3-RV-04, Revision 0, Regarding Repair Activities for Reactor Vessel Head Penetration Nozzles and Associated J-Groove Welds ML14363A4092015-01-28028 January 2015 Relief Request No. 1-TYP-4-RV-04 Regarding the Examination Requirements of Code Case N-729-1 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 ML1202702982012-02-0707 February 2012 Relief Request VRR3 Regarding Solenoid Operated Valve Remote Position Verification Frequency ML1131304282011-11-22022 November 2011 Relief Request VRR5 Regarding Turbine Driven Auxiliary Feedwater Valve Test Frequency for the 10-Year Inservice Testing Program Interval ML1126404122011-09-20020 September 2011 Acceptance Review Results for VC Summer Relief Request (ME6879) ML1113105612011-05-19019 May 2011 Acceptance of Requested Licensing Action Relief Request, Proposed Alternative to System Leakage Test Requirements ML1107705512011-04-26026 April 2011 Relief Request VRR2 Regarding the 10-Year Inservice Testing Program Interval ML1104705572011-02-25025 February 2011 Relief Request Regarding an Alternative Weld Repair Method for Reactor Vessel Head Penetrations J-Groove Welds ML1025715692010-09-20020 September 2010 Nozzle RR ML1006807812010-03-12012 March 2010 Third 10-Year ISI Interval Relief Request (ME2608) 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 2023-09-18
[Table view] Category:Letter
MONTHYEARIR 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 ML24025A0922024-01-25025 January 2024 Requalification Program Inspection 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-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023 Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615 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 ML23338A3172023-12-0606 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001 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 IR 05000334/20230112023-12-0404 December 2023 Age-Related Degradation Inspection Report 05000334/2023011 and 05000412/2023011 L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023 Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports IR 05000334/20233012023-11-27027 November 2023 Initial Operator Licensing Examination Report 05000334/2023301 L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 IR 05000334/20230032023-11-0606 November 2023 Integrated Inspection Report 05000334/2023003 and 05000412/2023003 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 L-23-227, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 20232023-10-20020 October 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 2023 L-23-215, Changes to Emergency Plan2023-10-19019 October 2023 Changes to Emergency Plan ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23198A3592023-10-0202 October 2023 Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - Nonproprietary IR 05000334/20234022023-09-29029 September 2023 Security Baseline Inspection Report 05000334/2023402 and 05000412/2023402 (Cover Letter Only) 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 ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure IR 05000334/20234012023-09-21021 September 2023 Cybersecurity Inspection Report 05000334/2023401 and 05000412/2023401 (Cover Letter Only) ML23263A0192023-09-20020 September 2023 Operator Licensing Examination Approval ML23243A9272023-09-19019 September 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23249A1842023-09-18018 September 2023 Authorization and Safety Evaluation for Alternative Request No. 2-TYP-4-RV-06 L-23-208, Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA00256152023-09-14014 September 2023 Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA0025615 L-23-167, Twenty-Third Refueling Outage Inservice Inspection Summary Report2023-09-13013 September 2023 Twenty-Third Refueling Outage Inservice Inspection Summary Report IR 05000346/20234012023-09-13013 September 2023 Security Baseline Inspection Report 05000346/2023401 (Public) L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments IR 05000334/20230052023-08-31031 August 2023 Updated Inspection Plan for Beaver Valley Power Station Units 1 and 2 (Report 05000334/2023005 and 05000412/2023005) L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual IR 05000346/20230112023-08-30030 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000346/2023011 ML23129A1722023-08-25025 August 2023 Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1 IR 05000346/20230052023-08-24024 August 2023 Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2023005) IR 05000334/20230022023-08-0909 August 2023 Integrated Inspection Report 05000334/2023002 and 05000412/2023002 ML23219A0592023-08-0707 August 2023 Steam Generator Inspection Reports - Spring 2023 Spring Refueling Outrage L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments IR 05000346/20230502023-08-0303 August 2023 Special Inspection Report 05000346/2023050 ML23178A2742023-08-0101 August 2023 Letter to the Honorable Marcy Kaptur from Chair Hanson Responds to Letter Regarding the License Transfer Application for the Davis-Besse Nuclear Power Station L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023 Submittal of Fifth Ten Year Inservice Testing Program IR 05000346/20230902023-08-0101 August 2023 EA-23-002 Davis-Besse Nuclear Power Station - NRC Inspection Report No. 05000346/2023090 (Public) IR 05000346/20230022023-07-27027 July 2023 Integrated Inspection Report 05000346/2023002 L-23-179, Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-07-18018 July 2023 Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA0025615 ML23188A0982023-07-17017 July 2023 Correction to the Safety Evaluation Issued Related to Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML23193A7842023-07-13013 July 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000346/2023402 ML23188A0672023-07-10010 July 2023 Project Manager Assignment 2024-02-02
[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 ML23198A3592023-10-0202 October 2023 Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - Nonproprietary 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) ML23249A1842023-09-18018 September 2023 Authorization and Safety Evaluation for Alternative Request No. 2-TYP-4-RV-06 ML23188A0982023-07-17017 July 2023 Correction to the Safety Evaluation Issued Related to Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML23102A1472023-05-22022 May 2023 Issuance of Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML23019A0032023-03-16016 March 2023 Issuance of Amendment Nos. 320 and 210 Adoption of Technical Specifications Task Force (Tstf) Traveler Tstf-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML23062A5212023-03-0606 March 2023 Issuance of Amendment No. 319 Revise Technical Specification (TS) 3.5.2, ECCS Operating, Limiting Condition for Operation (LCO) 3.5.2, 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 ML22277A8142022-10-0707 October 2022 Correction of Errors in Safety Evaluation Associated with License Amendment Nos. 315 and 205 Regarding Changes to the Emergency Preparedness Plan ML22210A0102022-09-16016 September 2022 Energy Harbor Fleet- Issuance of Amendments Regarding Adoption of TSTF 554, Revise Reactor Coolant Leakage Requirements ML22222A0862022-09-0101 September 2022 Issuance of Amendment Nos. 317 and 208 Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation ML22235A7672022-09-0101 September 2022 Correction of Errors in Safety Evaluation Associated with License Amendment Nos. 315 and 205 Regarding Changes to the Emergency Preparedness Plan ML22202A4642022-06-29029 June 2022 Emergency Plan Safety Evaluation ML22140A2092022-06-28028 June 2022 Issuance of Amendment No. 207 Correct TS 3.1.7 Change Made by TSTF-547 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 ML22095A2352022-05-10010 May 2022 Issuance of Amendment Nos. 316 and 206 Revise Technical Specification 5.6.3, Core Operating Limits Report (COLR) ML21286A7822022-05-0606 May 2022 Issuance of Amendment Nos. 315 and 205 Regarding Changes to the Emergency Plan ML22118B0382022-05-0505 May 2022 Proposed Alternative Request RP-4 Regarding the Inservice Testing of High-Pressure Injection Pumps ML22077A1342022-05-0202 May 2022 Issuance of Amendment Nos. 314 and 204 Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections 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 ML21197A0092021-11-0101 November 2021 Issuance of Amendment Nos. 313 and 203 Reactor Coolant System, Pressure and Temperature Limits Report ML21214A2752021-10-15015 October 2021 Issuance of Amendment Nos. 312 and 202 Atmospheric Dump Valves ML21153A1762021-06-30030 June 2021 Issuance of Amendment No. 201 Revision of Technical Specifications Related to Steam Generator Tube Inspection, and Repair Methods 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 ML21070A0002021-03-22022 March 2021 Issuance of Amendment 310, Revise Technical Specification 5.5.5.1, Unit 1 SG Program, to Defer Spring 2021 Refueling Outage Steam Generator Inspections to Fall 2022 Refueling Outage ML20346A0222021-03-10010 March 2021 Issuance of Amendment Nos. 309 and 199 to Change Technical Specifications to Implement New Surveillance Methods for the Heat Flux Hot Channel Factor ML20335A0522021-02-18018 February 2021 Issuance of Amendment Nos. 308 and 198 to Modify Certified Fuel Handler Related Technical Specifications for Permanently Defueled Condition ML20345A2362021-01-28028 January 2021 Issuance of Amendment Nos. 307 and 197 to Add Containment Sump Technical Specifications to Address GSI-191 Issues ML20335A0232020-12-28028 December 2020 Issuance of Amendment Nos. 306 and 196 to Remove License Conditions B and C Related to the Irradiated Fuel Management Plans ML20280A8272020-11-0303 November 2020 Issuance of Amendment No. 301 to Relocate Specific Surveillance Frequencies to a Licensee-Controlled Program ML20285A2662020-10-21021 October 2020 Correction to Safety Evaluation for Amendment Nos. 305 and 195 Issued September 23, 2020, Modify Primary and Secondary Coolant Activity Technical Specifications 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 ML20213A7312020-09-23023 September 2020 Issuance of Amendment Nos. 305 and 195 to Modify Primary and Secondary Coolant Activity Technical Specifications ML20213C7262020-08-24024 August 2020 Issuance of Amendment No. 300 to Revise the Containment Leakage Rate Testing Program ML20223A0142020-08-20020 August 2020 Issuance of Relief Request SSR-1, Revision 0, from the Requirements of the ASME Code (EPID L-2020-LLR-0050 (COVID-19)) ML20206K8652020-08-0707 August 2020 Relief Requests 2-TYP-4-RV-06 and 2-TYP-4-RV-07 from the Requirements of the ASME Code (EPID L-2020-LLR-0053 and EPID L-2020-LLR-0054 (COVID-19)) ML20153A0142020-07-16016 July 2020 Relief from the Requirements of the American Society of Mechanical Engineers Code Regarding Request VRR4 (EPID L-2020-LLR-0052 (COVID-19)) ML20145A0002020-06-0303 June 2020 Relief from the Requirements of the ASME Code for Requests VRR6 and VRR5 (EPID L-2020-LLR-0049 and EPID L-2020-LLR-0051 (COVID-19)) ML20080J7892020-04-28028 April 2020 Relief Requests 2 TYP-3-B3.110-1, 2-TYP-3-C2.21-1, 2-TYP-3-C1.30-1, and 2-TYP-3-RA-1 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval ML20079F8162020-03-26026 March 2020 Relief Requests 1-TYP-4-C2.21-1 and 1-TYP-4-RA-1 Regarding Weld Examination Coverage for the Fourth Inservice Inspection Interval ML19336A0282019-12-18018 December 2019 Safety Evaluation Irradiated Fuel Management Plans 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 ML19275E2942019-10-16016 October 2019 Issuance of Relief Request Proposed Alternative to Reactor Vessel Nozzle Weld Examination Frequency Requirements in Lieu of Specific ASME Code Requirements ML19100A3062019-06-21021 June 2019 Issuance of Amendment No. 298 to Adopt National Fire Protection Association Standard 805 2024-01-17
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March 29, 2022 Mr. David B. Hamilton Executive Vice President and Chief Nuclear Officer Energy Harbor Nuclear Corp.
168 E. Market Street Akron, OH 44308-2014
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2, AND DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 - CORRECTION LETTER - ISSUANCE OF AUTHORIZATION OF PROPOSED ALTERNATIVE TO USE ASME OM CODE CASE OMN-27 (EPID L-2021-LLR-0026)
Dear Mr. Hamilton:
By letter dated April 1, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21091A259), Energy Harbor Nuclear Corporation (the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the use of an alternative to certain Inservice Testing (IST) Program requirements of the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code), at Davis-Besse Nuclear Power Station (DBNPS) and Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS-1 and BVPS-2, respectively).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.55a(z)(1), the licensee requested to use Alternative Request RV-2 for DBNPS, Alternative Request VRR5 for BVPS-1, and Alternative Request VRR7 for BVPS-2, regarding valve IST, ASME OM Code Case OMN-27, Alternative Requirements for Testing Category A Valves (Non-PIV [pressure isolation valve]/CIV [containment isolation valve]), to determine valve test frequency in lieu of the 2-year leakage rate test frequency requirement specified in ASME OM Code Section ISTC-3630(a) for Category A valves that are not reactor coolant system PIVs or CIVs on the basis that the proposed alternative would provide an acceptable level of quality and safety.
By letter dated January 21, 2022 (ADAMS Accession No. ML222012A297), the NRC staff concluded that the licensee has adequately addressed the regulatory requirements set forth in 10 CFR 50.55a(z)(1) for Alternative Requests RV-2, VRR5, and VRR7 for DBNPS, BVPS-1, and BVPS-2, respectively. Therefore, the NRC staff authorized the use of Alternative Request RV-2 for DBNS, Alternative Request VRR5 for BVPS-1, and Alternative Request VRR7 for BVPS-2 for the remainder of the fourth 10-year IST program interval at DBNS, the remainder of the fifth 10-year IST program interval at BVPS-1, and the remainder of the fourth 10-year program interval at BVPS-2, which ends on September 20, 2022, September 19, 2027, and September 19, 2027, respectively.
D. Hamilton On March 18, 2022 (ADAMS Accession No. ML22080A251), the licensee informed the NRC of editorial inconsistencies in the safety evaluation (SE). The enclosure to this letter provides the corrected SE.
There is no change in the NRC authorization of the request. We apologize for the inconvenience.
If you have any questions, please contact the Project Manager, Bhalchandra Vaidya at 301-415-3308 or via e-mail at Bhalchandra.Vaidya@nrc.gov.
Sincerely, Digitally signed by Scott P. Wall Scott P. Wall Date: 2022.03.29 14:27:30 -04'00' Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334, 50-412, 50-346
Enclosure:
Corrected Safety Evaluation cc: ListServ
CORRECTED SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION PROPOSED ALTERNATIVE REQUESTS RV-2, VRR5, AND VRR7 REGARDING FOURTH 10-YEAR INSERVICE TESTING INTERVAL PROGRAM FOR DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1, FIFTH 10-YEAR INSERVICE TESTING INTERVAL PROGRAM FOR BEAVER VALLEY POWER STATION, UNIT NO. 1 FOURTH 10-YEAR INTERVAL INSERVICE TESTING PROGRAM FOR BEAVER VALLEY POWER STATION, UNIT NO. 2 ENERGY HARBOR NUCLEAR CORP.
DOCKET NOS. 50-346, 50-344, AND 50-412 EPID L-2021-LLR-0026
1.0 INTRODUCTION
By letter dated April 1, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21091A259), Energy Harbor Nuclear Corp. (Energy Harbor, the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the use of an alternative to certain inservice testing (IST) program requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), at Davis-Besse Nuclear Power Station (DBNPS) and Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS-1 and BVPS-2, respectively).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.55a(z)(1), the licensee requested to use Alternative Request RV-2 for DBNPS, Alternative Request VRR5 for BVPS-1, and Alternative Request VRR7 for BVPS-2, regarding valve IST, on the basis that the proposed alternative would provide an acceptable level of quality and safety.
Enclosure
2.0 REGULATORY EVALUATION
Paragraph 50.55a(f)(4) of 10 CFR, Inservice testing standards requirement for operating plants, states, 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 inservice test requirements (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.
The regulations in 10 CFR 50.55a(z), Alternatives to codes and standards requirements, state, in part, that alternatives to the requirements of 10 CFR 50.55a(f) may be used, when authorized by the NRC, if the licensee demonstrates: (1) the proposed alternatives would provide an acceptable level of quality and safety or (2) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the 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 NRC to authorize, the proposed alternative requested by the licensee.
3.0 TECHNICAL EVALUATION
The DBNPS fourth 10-year IST program interval began on September 21, 2012, and is scheduled to end on September 20, 2022. The BVPS-1 fifth 10-year IST program interval began on September 20, 2017, and is scheduled to end on September 19, 2027. The BVPS-2 fourth 10-year IST program interval began on September 20, 2017, and is scheduled to end on September 19, 2027. The applicable ASME OM Code edition and addenda for all three 10-year IST program intervals is the 2004 Edition through 2006 Addenda, which are incorporated by reference in 10 CFR 50.55a with conditions.
3.1 Licensees Alternative Requests RV-2, VRR5, and VRR7 ASME OM Code, Subsection ISTC, Inservice Testing of Valves in Light-Water Reactor Nuclear Power Plants, paragraph ISTC-3630, Leakage Rate for Other Than Containment Isolation Valves, subparagraph (a), Frequency, states, Tests shall be conducted at least once every 2 years.
The licensee requested to use the proposed alternative described below for all ASME OM Code Category A valves, excluding reactor coolant system (RCS) pressure isolation valves (PIVs) and containment isolation valves (CIVs), in their IST program that meet the requirements of ASME OM Code Case OMN-27, Alternative Requirements for Testing Category A Valves (Non-PIV/CIV).
ASME OM Code, Subsection ISTC, paragraph ISTC-1300, Valve Categories, defines Category A valves as valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their required function(s), as specified in paragraph ISTA-1100, Scope.
3.1.1 Reason for Request The licensee states that ASME OM Code Case OMN-27 establishes requirements for implementing and maintaining an ASME OM Code Category A valve performance-based leakage test methodology that may be implemented in lieu of the 2-year leakage rate test interval required per ASME OM Code, Subsection ISTC, subparagraph ISTC-3630(a). Code Case OMN-27 has not been approved for use in Regulatory Guide (RG) 1.192, Operation and Maintenance Code Case Acceptability, ASME OM Code, Revision 3, dated October 2019.
3.1.2 Proposed Alternative The licensee proposes to apply the ASME OM Code Case OMN-27 provisions in their entirety for implementing and maintaining a performance-based valve leakage test methodology as an alternative to the biennial valve leakage rate test interval required by ASME OM Code, Subsection ISTC, subparagraph ISTC-3630(a). This will apply to all ASME OM Code Category A valves except RCS PIVs and CIVs.
The plant staff at DBNPS, BVPS-1, and BVPS-2, have been testing their Category A valves, excluding RCS PIVs and CIVs, every 2 years, so this trending history provides justification to implement ASME OM Code Case OMN-27 for these valves.
3.2 NRC Staff Evaluation The licensee proposes to apply ASME OM Code Case OMN-27 in its entirety for all Category A valves that are not RCS PIVs or CIVs, at DBNPS, BVPS-1, and BVPS-2. These valves are identifiable in the IST program plans for DBNPS, BVPS-1, and BVPS-2. Code Case OMN-27 is applicable to the 1998 Edition through the 2020 Edition of the ASME OM Code, which includes the licensees Code of Record for the three 10-year IST program intervals described above (2004 Edition through 2006 Addenda of the ASME OM Code). The Code Case has been approved by the ASME OM Standards Committee, with the NRC staff representative voting in the affirmative. The Code Case has also been approved by the ASME Board of Nuclear Codes and Standards.
In response to the alternative requests for DBNPS, BVPS-1, and BVPS-2, the NRC staff has reviewed ASME OM Code Case OMN-27 and considers it to be acceptable for use by the licensee. Further, the NRC staff has proposed to include Code Case OMN-27 in the ongoing Revision 4 to RG 1.192 as acceptable for use. The NRC staff has not proposed any conditions on the use of Code Case OMN-27.
Based on its review, the NRC staff finds that allowing the use of Code Case OMN-27 provides an acceptable level of quality and safety for the ASME OM Code Category A valves, excluding RCS PIVs and CIVs, because this alternative will provide adequate indication of valve performance. If test results for a valve exceed the allowable acceptance criteria, the valve will be returned to the initial 2-year test interval.
4.0 CONCLUSION
As set forth above, the NRC staff has determined that Alternative Requests RV-2, VRR5, and VRR7 for DBNPS, BVPS-1, and BVPS-2, respectively, provide an acceptable level of quality and safety for the ASME OM Code Category A valves, excluding RCS PIVs and CIVs. These valves are identifiable in the IST program plans for DBNPS, BVPS-1, and BVPS-2.
Accordingly, the NRC staff concludes that the licensee has adequately addressed the regulatory requirements set forth in 10 CFR 50.55a(z)(1) for Alternative Requests RV-2, VRR5, and VRR7 for DBNPS, BVPS-1, and BVPS-2, respectively. Therefore, the NRC staff authorizes the use of Alternative Request RV-2 for DBNPS, Alternative Request VRR5 for BVPS-1, and Alternative Request VRR7 for BVPS-2, for the remainder of the fourth 10-year IST program interval at DBNPS, the remainder of the fifth 10-year IST program interval at BVPS-1, and the remainder of the fourth 10-year program interval at BVPS-2, which ends on September 20, 2022, September 19, 2027, and September 19, 2027, respectively.
All other ASME OM Code requirements for which relief or an alternative was not specifically requested and granted or authorized (as applicable) as part of this request remain applicable.
Principal Contributor: Robert Wolfgang, NRR/DEX/EMIB Date: March 29, 2022
ML22082A253 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/EMIB/BC NRR/DORL/LPL3/BC(A)
NAME BVaidya SRohrer ITseng NSalgado (SWall for)
DATE 03/24/2022 03/24/2022 03/24/2022 03/29/2022