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MONTHYEARML20224A2982020-08-20020 August 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI Project stage: Other 2020-08-20
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MONTHYEARIR 05000272/20230042024-02-0505 February 2024 Integrated Inspection Report 05000272/2023004 and 05000311/2023004 ML24030A8752024-02-0101 February 2024 Operator Licensing Examination Approval IR 05000354/20230042024-02-0101 February 2024 Integrated Inspection Report 05000354/2023004 ML24009A1022024-01-26026 January 2024 Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000272/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000272/2023401 and 05000311/2023401 IR 05000354/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000354/2023401 ML23341A1372024-01-16016 January 2024 Issuance of Amendment No. 235 Revise Trip and Standby Auto-Start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning ML24004A1542024-01-0808 January 2024 Notification of Conduct of a Fire Protection Team Inspection ML23307A1532023-12-15015 December 2023 NRC Investigation Report No. 1-2023-001 ML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers LR-N23-0079, Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days2023-12-0707 December 2023 Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days LR-N23-0077, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion2023-11-29029 November 2023 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement ML23324A3072023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000272/20230032023-11-13013 November 2023 Integrated Inspection Report 05000272/2023003 and 05000311/2023003 IR 05000354/20230032023-11-0707 November 2023 Integrated Inspection Report 05000354/2023003 LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 IR 05000272/20234022023-10-12012 October 2023 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023402, 05000272/2023402 and 05000311/2023402 (Cover Letter Only) IR 05000272/20230102023-10-12012 October 2023 Biennial Problem Identification and Resolution Inspection Report O5000272/2023010 and 05000311/2023010 LR-N23-0065, Submittal of 2023 Annual 10 CFR 50.46 Report2023-10-0202 October 2023 Submittal of 2023 Annual 10 CFR 50.46 Report LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement ML23249A2612023-09-0606 September 2023 License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000272/20230052023-08-31031 August 2023 Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023005 and 05000311/2023005) IR 05000354/20230052023-08-31031 August 2023 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2023005) ML23233A0762023-08-21021 August 2023 Requalification Program Inspection ML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location IR 05000272/20230022023-08-0909 August 2023 Integrated Inspection Report 05000272/2023002 and 05000311/2023002 LR-N23-0055, Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days2023-08-0303 August 2023 Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days IR 05000354/20230022023-08-0303 August 2023 Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001 IR 05000354/20230102023-08-0303 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000354/2023010 LR-N23-0052, Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.12023-07-31031 July 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.1 LR-N23-0054, In-Service Inspection Activities2023-07-26026 July 2023 In-Service Inspection Activities LR-N23-0042, Spent Fuel Cask Registration2023-07-12012 July 2023 Spent Fuel Cask Registration LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 LR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-06-23023 June 2023 License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML23139A1472023-06-0505 June 2023 Relief Request Associated with Fourth Interval In-service Inspection Limited Examinations of Weld Coverage ML23096A1842023-05-0909 May 2023 Issuance of Amendment No. 328 Revise and Relocate Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report IR 05000272/20230012023-05-0303 May 2023 Integrated Inspection Report 05000272/2023001 and 05000311/2023001 ML23081A4662023-05-0202 May 2023 Issuance of Amendment Nos. 346 and 327 Revise Technical Specifications to Extend Allowable Outage Time for Inoperable Emergency Diesel Generator IR 05000272/20233012023-05-0101 May 2023 Initial Operator Licensing Examination Report 05000272/2023301 and 05000311/2023301 ML23121A1412023-05-0101 May 2023 Senior Reactor and Reactor Operator Initial License Examinations IR 05000354/20230112023-05-0101 May 2023 Commercial Grade Dedication Report 05000354/2023011 LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station LR-N23-0033, Core Operating Limits Report Cycle 272023-04-26026 April 2023 Core Operating Limits Report Cycle 27 IR 05000354/20230012023-04-26026 April 2023 Integrated Inspection Report 05000354/2023001 LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location LR-N23-0009, License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains2023-04-18018 April 2023 License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains ML23087A1492023-04-17017 April 2023 NRC to PSEG Salem, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek 2024-02-05
[Table view] Category:Safety Evaluation
MONTHYEARML23341A1372024-01-16016 January 2024 Issuance of Amendment No. 235 Revise Trip and Standby Auto-Start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning ML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location ML23139A1472023-06-0505 June 2023 Relief Request Associated with Fourth Interval In-service Inspection Limited Examinations of Weld Coverage ML23096A1842023-05-0909 May 2023 Issuance of Amendment No. 328 Revise and Relocate Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report ML23081A4662023-05-0202 May 2023 Issuance of Amendment Nos. 346 and 327 Revise Technical Specifications to Extend Allowable Outage Time for Inoperable Emergency Diesel Generator ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership ML23044A1052023-03-13013 March 2023 Issuance of Amendment Nos. 345 and 326 Relocate Technical Specifications Requirements for Reactor Head Vents to Technical Requirements Manual ML23037A9712023-03-0909 March 2023 and Salem Nuclear, Unit Nos. 1 and 2 Issuance of Amendment Nos. 233, 344, and 325 Relocate Technical Specification Staff Qualification Requirements to the PSEG Quality Assurance Topical Report ML23019A3482023-02-0202 February 2023 Issuance of Relief Request No. SC-I5R-221 for the Alternative Repair for Service Water System Piping ML22194A8172022-08-10010 August 2022 Issuance of Amendment No. 232 Revise Surveillance Requirements for Electric Power Monitor Channels for Reactor Protection System and Power Range Neutron Monitoring System ML22194A8402022-07-15015 July 2022 Correction Letter of Relief Request No. HR-I4R-220 Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs ML22181A1252022-07-0505 July 2022 Issuance of Relief Request No. HR I4R-220 Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs ML22130A7912022-05-24024 May 2022 Issuance of Relief Request No. S1-I4R-210 Fourth Inservice Inspection Interval Limited Examinations ML22061A0302022-04-0404 April 2022 Issuance of Amendment Nos. 343 and 324 Revise Technical Specifications Surveillance Requirements for Auxiliary Feedwater ML21348A7132022-03-14014 March 2022 Issuance of Amendment No. 231 Revision of Technical Specification Limits for Ultimate Heat Sink ML22012A4352022-02-14014 February 2022 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendments Nos. 230, 342, and 323 Delete Definition in 10 CFR 20 and Figures of Site and Surrounding Areas ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21295A2292021-11-15015 November 2021 Issuance of Amendment Nos. 340 and 321 Revise Technical Specifications to Adopt TSTF 569, Revision of Response Time Testing Definitions ML21230A0182021-10-0808 October 2021 Issuance of Amendment No. 339 Revise and Relocate Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report ML21202A0782021-09-0303 September 2021 Issuance of Amendment Nos. 338 and 320 Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21181A0562021-08-17017 August 2021 Issuance of Amendment No. 229 Revise Low Pressure Safety Limit to Address General Electric Nuclear Energy Part-21 Safety Communication SC05-03 (EPID L 2020 Lla 0210) (Non-Proprietary) ML21195A0622021-08-0303 August 2021 Issuance of Amendment No. 319 One-Time Request to Revise Technical Specification Action for Rod Position Indicators ML21110A0522021-07-19019 July 2021 Issuance of Amendment Nos. 337 and 318, Revise Technical Specifications to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec ML21145A1892021-06-10010 June 2021 Authorization and Safety Evaluation for Alternative Request No. SC-I4R-200 ML21098A0872021-04-26026 April 2021 Issuance of Amendment No. 228 Adopt Technical Specifications Task Force TSTF-427, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability ML21050A0022021-03-12012 March 2021 Issuance of Amendment No. 227 Revise Technical Specifications to Adopt Technical Specifications Task Force Traveler TSTF-582, RPV WIC Enhancements ML21047A3132021-03-10010 March 2021 Issuance of Amendment No. 226 Revise Emergency Core Cooling System Technical Specification for High Pressure Coolant Injection System Inoperability (Non-Proprietary) ML20338A0382021-02-23023 February 2021 Issuance of Amendment Nos. 336 and 317 Leak-Before-Break for Accumulator, Residual Heat Removal, Safety Injection, and Pressurizer Surge Lines ML20281A6132020-11-0909 November 2020 Issuance of Amendment No. 225 Revise Technical Specification Actions for Suppression Pool Cooling ML20231A6322020-09-29029 September 2020 Issuance of Amendment No. 224 Regarding Adoption of 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components of Nuclear Power Reactors ML20224A2982020-08-20020 August 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20191A2032020-08-0606 August 2020 Issuance of Amendment Nos. 335 & 316-Revise Minimum Required Channels, Mode Applicability, & Actions for Source Range/Intermediate Range Neutron Flux Reactor Trip System Instrumentation ML20104A1862020-04-20020 April 2020 Issuance of Alternative Request SC-I4R-192 for Examination of ASME Code, Section XI, Steam Generator and Pressurizer Nozzle Inside Radius Sections ML20099E2332020-04-20020 April 2020 Issuance of Alternative Request S1-I4R-191 for the Fourth 10-Year Inservice Inspection Interval ML20091K7302020-04-13013 April 2020 Issuance of Relief Request SC-I4R-190 for the Fourth 10-Year Inservice Inspection Interval ML20091L9992020-04-13013 April 2020 Issuance of Relief Request HC-I4R-190 for the Fourth 10-Year Inservice Inspection Interval ML20034E6172020-02-27027 February 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 222, 333, and 314 Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions and License Transfer ML19352F2312020-02-18018 February 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2; Issuance of Amendment Nos. 221, 332, and 313 Revise Emergency Plan Staffing Requirements ML19330F1562020-01-14014 January 2020 Issuance of Amendment Nos. 331 and 312 Revise Technical Specifications to Adopt TSTF-563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19275D6942019-11-18018 November 2019 Issuance of Amendment Nos. 330 and 311 Revise Technical Specifications to Adopt TSFT-547, Clarification of Rod Position Requirements ML19289A8862019-11-0707 November 2019 Issuance of Amendment No. 220 Regarding Revise Technical Specifications to Adopt TSTF-546, Revise APRM (Average Power Range Monitor) Channel Adjustment Surveillance Requirement ML19218A3052019-09-19019 September 2019 Issuance of Amendment No. 219 Regarding Revise Technical Specifications to Adopt TSFF-564, Safety Limit MCPR ML19205A3062019-09-0606 September 2019 Issuance of Amendment No. 218 Regarding Revised Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements ML19220A1022019-09-0606 September 2019 Alternative Request VR-03 to Use ASME Code Case OMN-17, Alternative Rules for Testing ASME Class 1 Pressure Relief/Safety Valve for the Fourth 10-Year Inservice Test Interval ML19186A2052019-08-0606 August 2019 Issuance of Amendment No. 217 Remote Shutdown System ML19136A0262019-07-11011 July 2019 Issuance of Relief Request No. HC-I3R-08, Revision 0, Use of the ASME Code ML19105B1712019-05-31031 May 2019 Issuance of Amendment Nos. 329 and 310 Revise Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation, Main Steam Isolation Valves, and Add New TS ML19073A0732019-04-30030 April 2019 Issuance of Amendment No. 216 Revise Technical Specification 3/4.8.1, A.C. Sources - Operating, Action for Inoperable Diesel Generator ML19077A3362019-04-11011 April 2019 Issuance of Amendment Nos. 328 and 309 Revise Technical Specifications to Extend Refueling Water Storage Tank Allowed Outage Time ML19065A1562019-03-27027 March 2019 Issuance of Amendment No. 215 Inverter Allowed Outage Time Extension 2024-01-16
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August 20, 2020 Mr. Eric Carr President and Chief Nuclear Officer PSEG Nuclear LLC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GENERATING STATION AND SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 - REQUEST TO USE A PROVISION OF A LATER EDITION OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE, SECTION XI (EPID L-2020-LLR-0105)
Dear Mr. Carr:
By letter dated August 6, 2020 (Agencywide Documents Access and Management System Accession No. ML20219A638), PSEG Nuclear LLC (PSEG, the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) to use a provision of a later edition of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code,Section XI, for Hope Creek Generating Station (Hope Creek), and Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(4)(iv),
PSEG requested to use IWA-4540(b) of the 2017 Edition of the ASME BPV Code,Section XI, in place of the code of record.
The NRC staff authorizes the use of IWA-4540(b) of the 2017 Edition of ASME BPV Code,Section XI, for the duration of the fourth inservice inspection (ISI) intervals for Salem, Unit Nos.1 and 2, and Hope Creek, and the fifth ISI interval for Salem, Unit Nos. 1 and 2.
The fourth ISI interval for Salem, Unit No. 1, started on May 20, 2011, and ends on December 31, 2020. The fourth ISI interval for Salem, Unit No. 2, started on November 27, 2013, and ends on December 31, 2021. The fourth ISI interval for Hope Creek started on December 13, 2017, and ends on December 31, 2026. The fifth ISI intervals for Salem, Unit No. 1 and 2, start on January 1, 2021, and end on December 31, 2030. The overlap of the end and start dates for the Salem, Unit No. 2, fourth and fifth intervals is intentional to align Intervals for both Salem units.
All other ASME BPV Code,Section XI requirements which are not modified by the staffs approval of the licensees request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
E. Carr If you have any questions, please contact the Project Manager, James Kim, at 301-415-4125 or by e-mail to James.Kim@nrc.gov.
Sincerely, Digitally signed by James James G. G. Danna Date: 2020.08.20 Danna 13:19:00 -04'00' James G. Danna, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-354, 50-272, and 50-311 Enclosure Safety Evaluation cc: Listserv
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST TO USE A PROVISION OF A LATER EDITION OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE PSEG NUCLEAR LLC HOPE CREEK GENERATING STATION AND PSEG NUCLEAR LLC EXELON GENERATION COMPANY, LLC SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-354, 50-272, AND 50-311
1.0 INTRODUCTION
By letter dated August 6, 2020 (Agencywide Documents Access and Management System Accession No. ML ML20219A638), PSEG Nuclear LLC (PSEG, the licensee) submitted a request to use a provision of a later edition of the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel (BPV) Code,Section XI, for Hope Creek Generating Station (Hope Creek) and Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(4)(iv),
the licensee proposed to use subparagraph IWA-4540(b) of the 2017 Edition of the ASME BPV Code instead of the corresponding subparagraph from the current code of record. The time period applicable for the use of the requested subsequent ASME BPV Code edition and addenda is the fourth and fifth inservice inspection (ISI) interval. The licensee asserts that it meets all related requirements of the 2017 Edition of the ASME BPV Code.
2.0 PROPOSED USE OF SUBSEQUENT CODE EDITION AND ADDENDA 2.1 Components for Which the Subsequent Code Edition is Requested All Class 1, 2, and 3 items located in the ASME BPV Code,Section XI, boundaries.
Enclosure
2.2 Current Code Requirement Subparagraph IWA-4540(b) provides items that are exempt from pressure testing after repair/replacement activities.
2.3 Current Code Edition and Addenda of Record The licensee provided the code of record and the duration of the fourth and fifth ISI intervals in the table below. The shifting of the 2013 Edition interval start and end dates for Salem, Unit No.
2, in the table is intentional to align intervals for both Salem units as allowed by the code.
Plant 10-Year ASME Code of Interval Interval End ISI Interval Record Start Salem, Unit 1 4 2004 Edition 05/20/2011 12/31/2020 5 2013 Edition 01/01/2021 12/31/2030 Salem, Unit 2 4 2004 Edition 11/27/2013 12/31/2021 5 2013 Edition 01/01/2021 12/31/2030 Hope Creek 4 2007 Edition, through 12/13/2017 2/31/2026 2008 Addenda 2.4 Proposed Subsequent Code Edition and Addenda The proposed subsequent code edition and addenda to be used is Subparagraph IWA-4540(b) of the 2017 Edition of the ASME BPV Code,Section XI.
2.5 Duration of the Use of the Later Code Edition and Addenda The duration of this request is for the fourth ISI intervals for Salem, Unit Nos.1 and 2, and Hope Creek, and the fifth ISI interval for Salem, Unit Nos. 1 and 2.
3.0 REGULATORY EVALUATION
This section of the safety evaluation considers only the regulatory basis for the licensees request. The technical merits of the licensees submission are addressed in later sections of this safety evaluation.
The licensee is proposing to use a section of a later edition and addenda of the ASME BPV Code in accordance with 10 CFR 50.55a(g)(4)(iv), which 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.
Given that 10 CFR 50.55(g)(4)(iv) permits the U.S. Nuclear Regulatory Commission (NRC) staff to approve the use of subsequent ASME BPV Code edition and addenda, the NRC staff finds that, subject to the following technical evaluation, the licensee may propose to use a section of a later edition and addenda of the ASME BPV Code,Section XI, and the NRC staff has the
regulatory authority to approve the later edition and addenda of the ASME BPV Code,Section XI.
4.0 NRC TECHNICAL EVALUATION As previously stated in Section 3.0 of this safety evaluation, prior to approving the use of a subsequent edition and addenda of the ASME BPV Code under 10 CFR 50.55a(g)(4)(iv), the NRC staff must find that (1) the proposed subsequent edition and addenda are incorporated by reference in 10 CFR 50.55a(a); (2) the licensee has identified any conditions listed in 10 CFR 50.55a(b) appropriate to the request and will comply with those conditions; (3) the licensee has requested approval to use the subsequent edition and addenda; and (4) if only portions of edition or addenda are to be used, all related requirements of the respective edition or addenda are met. If these criteria are met, the NRC staff finds the use of the subsequent edition and addenda of the ASME BPV Code,Section XI, to be acceptable.
4.1 Incorporation by Reference In evaluating the first criterion, 10 CFR 50.55a(a) incorporates by reference the ASME BPV Code,Section XI, from the 1970 Edition through the 1976 Winter Addenda, and the 1977 Edition through the 2017 Edition. The licensee proposed to use the 2017 Edition, which is included in the list of editions and addenda incorporated by reference in the current edition of 10 CFR 50.55a(a). Therefore, the NRC staff finds that the first criterion has been satisfied.
4.2 Subject to Conditions Listed in 10 CFR 50.55a(b)
In evaluating the second criterion, the NRC staff finds that 10 CFR 50.55a(b) contains no conditions relevant to this request. Therefore, the NRC staff finds that the second criterion has been satisfied.
4.3 Requesting Commission Approval In evaluating the third criterion, the licensees request dated August 6, 2020, constitutes a request to the Commission for approval to use a subsequent edition/addendum of the ASME BPV Code,Section XI. Therefore, the NRC staff finds that the third criterion has been satisfied.
4.4 All Related Requirements In evaluating the fourth criterion, the NRC staff finds that there are no related requirements relevant to this request. Therefore, the NRC staff finds that the fourth criterion has been satisfied.
4.5 Summary Based on the review above, the NRC staff finds that the licensee has adequately addressed all regulatory requirements set forth in 10 CFR 50.55a(g)(4)(iv).
5.0 CONCLUSION
As set forth above, NRC staff finds that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(g)(4)(iv). Therefore, the NRC staff concludes that the use of Section IWA-4540(b) the 2017 Edition of the ASME BPV Code,
Section XI is acceptable. The NRC staff authorizes the use of IWA-4540(b) of the 2017 Edition of the ASME BPV Code,Section XI, for the duration of the fourth ISI intervals for Salem, Unit Nos.1 and 2, and Hope Creek, and the fifth ISI interval for Salem, Unit Nos. 1 and 2.
All other ASME BPV Code,Section XI requirements which are not modified by the staffs approval of the licensees request remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: J. Kim Date: August 20, 2020
ML20224A298 OFFICE DORL/LPL1/PM DORL/LPL1/LA DNRL/NPHP/BC DORL/LPL1/BC DORL/LPL1/PM NAME JKim LRonewicz MMitchell JDanna JKim DATE 08/13/2020 08/13/2020 08/17/2020 08/20/2020 08/20/2020