Letter Sequence Request |
|---|
EPID:L-2020-LLA-0132, Request to Use Provision in Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (Approved, Closed) |
|
MONTHYEARML20198M4432020-07-16016 July 2020
NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Acceptance of License Amendment Request Regarding Request to Modify Technical Specification 3.3.3-1 Post Accident Monitoring Instrumentation
Project stage: Acceptance Review
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
Project stage: Request
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
Project stage: Other
ML21084A1902021-05-0404 May 2021
Issuance of Amendment Nos. 355 and 348 Regarding Revision to Technical Specification Table 3.3.3-1, Post Accident Monitoring Instrumentation
Project stage: Approval
2020-07-16
[Table View] |
|
|---|
Category:Code Relief or Alternative
MONTHYEARML23249A1842023-09-18018 September 2023
Authorization and Safety Evaluation for Alternative Request No. 2-TYP-4-RV-06
ML22252A2212022-09-30030 September 2022
Authorization and Safety Evaluation for Alternative Request IR-063
ML22187A2592022-07-12012 July 2022
Issuance of Relief Proposed Alternative Request Vr 12, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval
ML22136A1132022-06-21021 June 2022
Issuance of Relief Proposed Alternative Requests VR-10, Revision 0, and VR-11, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval (EPIDs L-2021-LLR-0096; L-2021-LLR-0097)
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
ML21123A2892021-05-0404 May 2021
Issuance of Relief Request Vr 7, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval
ML21110A6092021-04-26026 April 2021
Issuance of Relief Requests Vr 3, Revision 0, and Vr 5, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval
ML20363A0062021-01-29029 January 2021
Issuance of Relief Proposed Alternative Request Associated with Fourth 10-Year Inservice Inspection Interval
L-21-047, 10 CFR 50.55a Request Numbers VR-3 and VR-5, Valve Testing Extension2021-01-28028 January 2021
10 CFR 50.55a Request Numbers VR-3 and VR-5, Valve Testing Extension
ML20311A6582020-11-10010 November 2020
Issuance of Relief Proposed Alternative Request Associated with Fourth Ten Year Interval Inservice Inspection Interval
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
ML20266G2652020-09-24024 September 2020
Correction Letter for Relief Request IR-062 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval
ML20252A0262020-09-18018 September 2020
Relief Request IR-062 Regarding Weld Examination Coverage for the Third Inservice Inspection Interval
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))
ML20189A0032020-07-10010 July 2020
Relief Request PR-3 for Fourth 10-Year Pump and Valve Inservice Testing Program
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
ML20095J2192020-04-0404 April 2020
Email Beaver Valley Power Station, Unit 2 - Verbal Relief for MOVs - Delivered 4/4/2020 at 4:00 Pm
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
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-20-117, 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-20-060, 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
L-19-145, 10 CFR 50.55a Request in Support of the Fourth 10-Year Inservice Inspection (ISI) Interval2020-01-0606 January 2020
10 CFR 50.55a Request in Support of the Fourth 10-Year Inservice Inspection (ISI) 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
ML19072A0852019-03-15015 March 2019
Correction to Request for Alternatives Related to Inservice Testing Program for the Fourth 10 Year Inservice Testing Interval
ML19037A0412019-02-25025 February 2019
Request for Alternative to Use ASME Code Case N-831
ML19029A0902019-02-25025 February 2019
Request for Alternatives Related to Inservice Testing Program for the Fourth 10-Year Inservice Testing Interval (EPID Nos. L-2018-LLR-0092, 0093, 0094, 0095, and 0096)
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
ML18023A6252018-01-29029 January 2018
Approval of Alternative to Use BWRVIP Guidelines in Lieu of Certain ASME Code Requirements (CAC No. MG0149; EPID 2017-LLR-0112) (L-17-183)
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)
ML17270A0302017-10-16016 October 2017
Approval of Alternative to Use ASME Code Case N-513-4 for Repair of Emergency Service Water System Piping (CAC No. MG0130; EPID L-2017-LLR-0080)(L-17-278)
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
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
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)
2023-09-18
[Table view]
Category:Letter type:L
MONTHYEARL-24-017, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2024-01-24024 January 2024
30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative
L-23-207, License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2024-01-24024 January 2024
License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs
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-23-171, CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency2023-12-0808 December 2023
CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency
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
L-23-244, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
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
L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-23-238, Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 202023-11-10010 November 2023
Mid-Cycle Revision to the Core Operating Limits Report for Operating Cycle 20
L-23-052, Submittal of the Updated Safety Analysis Report, Revision 232023-10-27027 October 2023
Submittal of the Updated Safety Analysis Report, Revision 23
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
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
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
L-23-206, Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD2023-09-12012 September 2023
Ohio National Pollutant Discharge Elimination System (NPDES) Permit 3IB00016 MD
L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023
Quality Assurance Program Manual
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
L-23-001, License Amendment Request to Remove the Table of Contents from the Technical Specifications2023-08-0707 August 2023
License Amendment Request to Remove the Table of Contents from the Technical Specifications
L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023
Submittal of Fifth Ten Year Inservice Testing Program
L-23-174, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2023-07-19019 July 2023
30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative
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
L-23-146, License Renewal Application for the Perry Nuclear Power Plant2023-07-0303 July 2023
License Renewal Application for the Perry Nuclear Power Plant
L-23-165, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-06-26026 June 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-23-051, Plan, Nineteenth Inservice Inspection Summary Report2023-06-22022 June 2023
Plan, Nineteenth Inservice Inspection Summary Report
L-23-050, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-22022 June 2023
2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-23-034, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-13013 June 2023
2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-23-139, Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report2023-06-13013 June 2023
Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report
L-22-249, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener2023-06-0505 June 2023
License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener
L-23-135, Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-31031 May 2023
Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
L-23-055, Submittal of the Updated Final Safety Analysis Report, Revision 342023-05-23023 May 2023
Submittal of the Updated Final Safety Analysis Report, Revision 34
L-23-134, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-23023 May 2023
Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations
L-23-065, Annual Financial Report2023-05-22022 May 2023
Annual Financial Report
L-23-137, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-05-18018 May 2023
Discharge Monitoring Report (NPDES) Permit No. PA0025615
L-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023
Cycle 24 Core Operating Limits Report
L-23-101, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 20222023-05-12012 May 2023
Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 2022
L-23-131, Readiness for Resumption of NRC Supplemental Inspection2023-05-12012 May 2023
Readiness for Resumption of NRC Supplemental Inspection
L-23-132, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-10010 May 2023
Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations
L-23-129, Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations2023-05-0505 May 2023
Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations
L-23-092, Occupational Radiation Exposure Report for Year 20222023-04-27027 April 2023
Occupational Radiation Exposure Report for Year 2022
L-23-115, Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological2023-04-27027 April 2023
Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological
L-23-121, Annual Radiological Effluent Release Report2023-04-26026 April 2023
Annual Radiological Effluent Release Report
L-23-122, Annual Radiological Environmental Operating Report2023-04-26026 April 2023
Annual Radiological Environmental Operating Report
L-23-126, Discharge Monitoring Report (Npdes), Permit No. PA00256152023-04-22022 April 2023
Discharge Monitoring Report (Npdes), Permit No. PA0025615
L-23-053, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-04-14014 April 2023
2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023
Submittal of the Decommissioning Funding Status Reports
L-23-049, Core Operating Limits Report for Operating Cycle 202023-03-30030 March 2023
Core Operating Limits Report for Operating Cycle 20
L-23-037, and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2023-03-29029 March 2023
and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments
L-23-058, 180-Day Steam Generator Tube Inspection Report2023-03-27027 March 2023
180-Day Steam Generator Tube Inspection Report
2024-01-24
[Table view] |
Text
Energy Harbor Nuclear Corp.
168 E. Market Street Akron, Ohio 44308 Darin M. Benyak 330-436-1380 Vice President, Fleet Nuclear Operations September 28, 2020 L-20-256 10 CFR 50.55a Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit Nos. 1 and 2 Docket No. 50-334, License No. DPR-66 Docket No. 50-412, License No. NPF-73 Davis-Besse Nuclear Power Station, Unit No. 1 Docket No. 50-346, License No. NPF-3 Perry Nuclear Power Plant, Unit No. 1 Docket No. 50-440, License No. NPF-58 Request to Use Provision in Later Edition of the ASME Boiler and Pressure Vessel Code,Section XI In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (g)(4)(iv), and NRC Regulatory Issue Summary 2004-12, "Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI," Dated July 28, 2004, Energy Harbor Nuclear Corp. requests Nuclear Regulatory Commission (NRC) approval to use a specific provision of a later edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, for the units identified above. Specifically, Energy Harbor Nuclear Corp. requests approval to use IWA-4540(b) of the 2017 Edition of the ASME B&PV Code.
Energy Harbor Nuclear Corp. requests approval of this request by January 29, 2021 to support spring outages.
There are no regulatory commitments in this submittal. If there are any questions or if additional information required, please contact Phil H. Lashley, Manager - Fleet Licensing, at (330) 696-7208.
Respectfully, Darin M. Benyak
Beaver Valley Power Station, Unit Nos. 1 and 2 Davis-Besse Nuclear Power Station, Unit No. 1 Perry Nuclear Power Plant, Unit No. 1 L-20-256 Page 2
Enclosure:
10 CFR 50.55a(g)(iv) Request 20-027, Revision 0 cc: NRC Regions I Administrator NRC Regions III Administrator NRC Resident Inspector - Beaver Valley NRC Resident Inspector - Davis-Besse NRC Resident Inspector - Perry NRR Project Manager - Energy Harbor Nuclear Corp. Fleet Director BRP/DEP Site BRP/DEP Representative Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)
Utility Radiological Safety Board
L-20-256 Enclosure Beaver Valley Power Station, Unit Nos. 1 and 2 Davis-Besse Nuclear Power Station, Unit No. 1 Perry Nuclear Power Plant, Unit No. 1 10 CFR 50.55a(g)(4)(iv) Request 20-027, Revision 0 (2 Pages follow)
10 CFR 50.55a(g)(iv) Request 20-027, Revision 0 Page 1 of 2 Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)
- 1. ASME Code Component(s) Affected:
Class 1, 2, and 3 items located in the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code (ASME Code)Section XI boundaries.
2. Applicable Code Edition and Addenda
INTERVAL ISI ASME CODE INTERVAL PLANT SCHEDULED INTERVAL EDITION START END Beaver Valley Power 5 2013 Edition, No 08/29/2018 08/28/2028 Station, Unit No. 1 Addenda Beaver Valley Power 4 2013 Edition, No 08/29/2018 08/28/2028 Station, Unit No. 2 Addenda Davis-Besse Nuclear 4 2007 Edition through 09/21/2012 09/20/2022 Power Station, Unit 2008 Addenda No. 1 Perry Nuclear Power 4 2013 Edition, No 05/18/2019 05/17/2029 Plant, Unit No.1 Addenda
- 3. Proposed Subsequent Code Edition and Addenda (or Portion):
In accordance with 10 CFR 50.55a, "Codes and standards," paragraph (g)(4)(iv) and the guidance provided in Nuclear Regulatory Commission (NRC) Regulatory Issue Summary 2004-12 (Reference 1), Energy Harbor Nuclear Corp. requests NRC approval to use specific provisions of a later edition of the ASME Code,Section XI, for Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS), Perry Nuclear Power Plant, Unit No. 1 (PNPP), and Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS).
BVPS and PNPP perform Repair/Replacement activities in accordance with a fleet program based on the 2013 Edition of ASME Code,Section XI. DBNPS performs Repair/Replacement activities in accordance with a fleet program based on the 2007 Edition through the 2008 Addenda of ASME Code,Section XI.
Pursuant to 10 CFR 50.55a(g)(4)(iv), Energy Harbor Nuclear Corp. requests approval to use IWA-4540(b) from the ASME Code, 2017 Edition. This subparagraph outlines items that are exempt from pressure testing after repair/replacement activities.
Paragraph 10 CFR 50.55a(a) incorporates by reference the ASME Code,Section XI, 1977 Edition through the 2017 Edition. Therefore, IWA-4540(b) of the 2017 Edition of ASME Code Section XI, is included in the list of editions and addenda incorporated by reference in the current edition of 10 CFR 50.55a(a).
10 CFR 50.55a(g)(iv) Request 20-027, Revision 0 Page 2 of 2
- 4. Related Requirements:
10 CFR 50.55a(g)(4)(iv) states:
Inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (a) of this section, subject to the conditions listed in paragraph (b) of this section, and subject to Commission approval. Portions of editions or addenda may be used, provided that all related requirements of the respective editions or addenda are met.
10 CFR 50.55a(b)(2) incorporates by reference Section XI, Division 1, of the ASME Code 2017 Edition as approved in Reference 2. There are no related requirements or applicable conditions in 10 CFR 50.55a(b) or the ASME Code 2017 Edition associated with subparagraph IWA-4540(b).
- 5. Duration of Proposed Request:
The duration of this request is the remainder of each plants current inservice inspection interval listed above in Section 2, "Applicable Code Edition and Addenda."
- 6.
References:
- 1. NRC Regulatory Issue Summary 2004-12, Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section Xl, dated July 28, 2004
- 2. American Society of Mechanical Engineers 2015-2017 Code Editions Incorporation by Reference, 85 FR 26540, dated May 4, 2020