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EPID:L-2019-LLR-0090, Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange for Salem Generating Station and Hope Creek Generating Station (Approved, Closed) |
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Category:Code Relief or Alternative
MONTHYEARML22194A8402022-07-15015 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 ML20091L9992020-04-13013 April 2020 Issuance of Relief Request HC-I4R-190 for the Fourth 10-Year Inservice Inspection Interval 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 ML19136A0262019-07-11011 July 2019 Issuance of Relief Request No. HC-I3R-08, Revision 0, Use of the ASME Code LR-N18-0087, Submittal of Relief Request Associated with the Third Inservice Inspection (ISI) Interval2018-09-24024 September 2018 Submittal of Relief Request Associated with the Third Inservice Inspection (ISI) Interval ML17223A4832017-08-17017 August 2017 Relief from the Requirements of the ASME Code for Alternative to Nozzle-to-Vessel Weld and Inner Radius Examinations ML16343A0572016-12-20020 December 2016 Requests for Relief GR-01, PR-01, PR-02, VR-01, and VR-02, for the Fourth Inservice Testing Interval ML15281A1202015-11-0202 November 2015 Relief from the Requirements of the ASME Code ML0824700632008-10-16016 October 2008 Safety Evaluation of Relief Requests for the Third 10-Year Interval of the Inservice Inspection Program for Hope Creek Generating Station ML0515201772005-08-29029 August 2005 Evaluation of Relief Request HC-RR-I2-W01 ML0500302112005-08-0202 August 2005 Relief, HC-RR-12-30, MC5174 ML0420102502004-08-27027 August 2004 Evaluation of Relief Request HC-RR-12-023 ML0322504712003-08-26026 August 2003 Evaluation of Relief Request HC-RR-B08 ML0314204812003-05-15015 May 2003 Supplemental Information for Relief Request HC-RR-B11 ML0311300072003-04-14014 April 2003 Code Relief, Alternative to Required Volumetric Examination for Nozzles Where Plant Configuration Is Such That Visual Examination of Inner Radius May Be Performed on Essentially 100 Percent of Inner Radius ML0311300042003-04-14014 April 2003 Inservice Inspection Program Relief Request HC-RR-B12 ML0306901772003-02-20020 February 2003 Inservice Inspection Program Relief Request HC-RR-F02 ML0305903472003-02-20020 February 2003 Inservice Inspection Program Relief Request HC-RR-B08 ML0305902162003-02-20020 February 2003 Inservice Inspection Program Relief Request HC-RR-A02 ML0305902072003-02-20020 February 2003 Inservice Inspection Program Relief Request HC-RR-A06 2022-07-05
[Table view] Category:Letter
MONTHYEARIR 05000354/20230042024-02-0101 February 2024 Integrated Inspection Report 05000354/2023004 ML24030A8752024-02-0101 February 2024 Operator Licensing Examination Approval 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 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 ML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers ML23307A1532023-12-15015 December 2023 NRC Investigation Report No. 1-2023-001 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 05000354/20230032023-11-0707 November 2023 Integrated Inspection Report 05000354/2023003 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) 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 05000354/20230052023-08-31031 August 2023 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2023005) 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 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-N23-0042, 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 IR 05000354/20230112023-05-0101 May 2023 Commercial Grade Dedication Report 05000354/2023011 ML23121A1412023-05-0101 May 2023 Senior Reactor and Reactor Operator Initial License Examinations 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-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) 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 ML23089A0942023-04-17017 April 2023 NRC to PSEG Hope Creek, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23103A3232023-04-13013 April 2023 Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89 ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2023-03-29029 March 2023 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23086A0912023-03-24024 March 2023 NMFS to NRC, Transmittal of Biological Opinion for Continued Operations of Salem and Hope Creek Nuclear Generating Stations LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums 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 IR 05000354/20220062023-03-0101 March 2023 Annual Assessment Letter for Hope Creek Generating Station (Report 05000354/2022006) LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023 and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments LR-N23-0018, Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges2023-02-27027 February 2023 Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023 Annual Property Insurance Status Report LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023 Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717 IR 05000354/20220042023-01-24024 January 2023 Integrated Inspection Report 05000354/2022004 LR-N23-0011, In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage2023-01-19019 January 2023 In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage LR-N22-0096, and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination2023-01-0505 January 2023 and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022 Emergency Plan Document Revisions Implemented November 21, 2022 LR-N22-0091, Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments2022-12-0202 December 2022 Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments ML22335A0412022-12-0101 December 2022 Notification of Commercial Grade Dedication Inspection (05000354/2023011) and Request for Information IR 05000354/20220032022-11-0303 November 2022 Integrated Inspection Report 05000354/2022003 2024-02-01
[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 ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership 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 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 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 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) 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) 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 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 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 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 ML19205A3062019-09-0606 September 2019 Issuance of Amendment No. 218 Regarding Revised Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements 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 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 ML19065A1562019-03-27027 March 2019 Issuance of Amendment No. 215 Inverter Allowed Outage Time Extension ML19044A6272019-03-0606 March 2019 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 214, 327, and 308 Revise Technical Specifications to Adopt TSTF-529 ML18290A8762018-12-0606 December 2018 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC No. MF4458; EPID No. L-2014-JLD-0040) ML18260A2032018-10-30030 October 2018 Issuance of Amendment No. 213 Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control ML18096A5422018-04-24024 April 2018 Hope Creek Generating Station - Issuance of Amendment Measurement Uncertainty Recapture Power Uprate (CAC MF9930; EPID L-2017-LLS-0002) ML18081A0442018-04-11011 April 2018 Issuance of Amendment No. 211 Safety Limit Minimum Critical Power Ratio Change ML17355A5702018-02-16016 February 2018 Issuance of Amendment Nos. 322, 303, & 210, to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 (CAC Nos. MF9268/MF9269/MF9270; EPID L-2017-LLA-0173) ML17324A8402017-12-14014 December 2017 Issuance of Amendment to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report (CAC No. MF9502; EPID L-2017-LLA-0204) ML17317A6052017-12-13013 December 2017 Issuance of Amendment, License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-535 ML17321B1062017-11-28028 November 2017 Request to Use Later Edition of American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (CAC No. MG0124; EPID L-2017-LLR-0087) ML17291A2092017-11-0808 November 2017 Issuance of Amendment Technical Specification Change for Permanent Extension to Type a and Type C Containment Leak Rate Test Frequencies (CAC No. MF8462; EPID L-2016-JLD-0011) ML17223A4832017-08-17017 August 2017 Relief from the Requirements of the ASME Code for Alternative to Nozzle-to-Vessel Weld and Inner Radius Examinations ML17216A0222017-08-0404 August 2017 Nonproprietary Issuance of Amendment Regarding Digital Power Range Neutron Monitoring System Upgrade ML17125A2662017-06-30030 June 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17164A3552017-06-28028 June 2017 Issuance of Amendment to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing ML17093A8702017-05-16016 May 2017 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendments Revised PSEG Nulcear LLC Cyber Security Plan Milestone 8 Implementation Schedule ML17047A0202017-03-21021 March 2017 Issuance of Amendment to Delete Technical Specification Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves ML17053A1782017-03-15015 March 2017 Issuance of Amendment to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling ML17012A2922017-02-0606 February 2017 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Issuance of Amendments ML16343A0572016-12-20020 December 2016 Requests for Relief GR-01, PR-01, PR-02, VR-01, and VR-02, for the Fourth Inservice Testing Interval ML16270A0382016-10-13013 October 2016 Issuance of Amendment No. 200 Safety Limit Minimum Critical Power Ratio Change ML16256A6552016-09-30030 September 2016 Hope Creek Generating Station - Request for Relaxation of the Release Point Height Requirement of NRC Order EA-13-109,Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ML16259A2042016-09-20020 September 2016 Hope Creek Generating Station - Safety Evaluation - Request to revise technical specifications - safety limit minimum critical power ratio.(TAC NO. MF7793) ML15286A0912015-11-30030 November 2015 Issuance of Amendment Adoption of Technical Specifications Task Force Traveler-522 2024-01-16
[Table view] |
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April 13, 2020 Mr. Eric Carr President and Chief Nuclear Officer PSEG Nuclear LLC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK NUCLEAR GENERATING STATION - ISSUANCE OF RELIEF REQUEST HC-I4R-190 FOR THE FOURTH 10-YEAR INSERVICE INSPECTION INTERVAL (EPID L-2019-LLR-0090)
Dear Mr. Carr:
By letter dated September 11, 2019 (Agencywide Documents Access and Management System Accession No. ML19254A590), PSEG Nuclear LLC (the licensee) requested relief from the requirements of the American Society of the Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV Code) for Hope Creek Generating Station (Hope Creek). The licensees proposed alternative, HC-I4R-190, requests to eliminate the volumetric examination of the reactor pressure vessel threads in flange during the fourth 10-year inservice inspection interval at Hope Creek.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1), the licensee requested to use the proposed alternative in relief request HC-I4R-190 on the basis that the alternative provides an acceptable level of quality and safety.
The U.S Nuclear Regulatory Commission (NRC) staff has reviewed the subject request and concludes that for alternative request HC-I4R-190 for Hope Creek, the proposed alternative provides an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all the regulatory requirements set forth in 10 CFR 50.55a(z)(1) for alternative request. Therefore, the NRC staff authorizes the use of the alternative request HC-I4R-190 to eliminate the volumetric examination of the RPV threads in flange for the duration of the fourth 10-year ISI interval, which began on December 13, 2017, and is scheduled to end on December 31, 2026.
All other ASME B&PV Code, Section XI, requirements for which relief was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
E. Carr If you have any questions, please contact the Hope Creek Project Manager, James Kim, at 301-415-4125 or via e-mail to James.Kim@nrc.gov.
Sincerely,
/RA/
James G. Danna, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosure:
Safety Evaluation cc: Listserv
ML20091L999 *by e-mail OFFICE DORL/LPL1/PM DORL/LPL1/LA DNLR/NVIB/BC* DORL/LPL1/BC DORL/LPL1/PM NAME JKim LRonewicz HGonzalez JDanna JKim DATE 04/01/2020 03/31/2020 03/27/2020 4/13/2020 04/13/2020 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ALTERNATIVE REQUEST HC-I4R-190 FOR FOURTH 10-YEAR INTERVAL INSERVICE INSPECTION HOPE CREEK GENERATING STATION PSEG NUCLEAR LLC EXELON GENERATION COMPANY, LLC DOCKET NO. 50-354
1.0 INTRODUCTION
By letter dated September 11, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19254A590), PSEG Nuclear LLC (PSEG, the licensee) requested relief from the requirements of the American Society of the Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code (B&PV Code) for Hope Creek Generating Station (Hope Creek). The licensees proposed alternative, HC-I4R-190, requests to eliminate the volumetric examination of the reactor pressure vessel (RPV) threads in flange during the fourth 10-year inservice inspection (ISI) interval at Hope Creek.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(1), the licensee requested to use the proposed alternative in relief request HC-I4R-190 on the basis that the alternative provides an acceptable level of quality and safety.
2.0 REGULATORY EVALUATION
The regulations in 10 CFR 50.55a(g)(4) state, in part, that ASME B&PV Code Class 1, 2, and 3 components (including supports) must meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in Section XI of the applicable editions and addenda of the ASME B&PV Code to the extent practical within the limitations of design, geometry, and materials of construction of the components. The threads in the RPV flange are categorized as ASME B&PV Code Class 1 components. Therefore, per 10 CFR 50.55a(g)(4), ISI of these threads must be performed in accordance with Section XI of the applicable edition and addenda of the ASME B&PV Code.
The regulations in 10 CFR 50.55a(z), Alternatives to codes and standards requirements, state:
Alternatives to the requirements of paragraphs (b) through (h) of this section
[50.55a] or portions thereof may be used when authorized by the Director, Office Enclosure
of Nuclear Reactor Regulation. A proposed alternative must be submitted and authorized prior to implementation. The applicant or licensee must demonstrate that:
(1) Acceptable Level of Quality and Safety. The proposed alternative would provide an acceptable level of quality and safety; or (2) Hardship without a Compensating Increase in Quality and Safety.
Compliance with the specified requirements of this section [50.55a] 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 the licensee may propose an alternative to ASME B&PV Code, Section XI, and the NRC staff has the regulatory authority to authorize the licensees proposed alternative.
3.0 TECHNICAL EVALUATION
3.1 Licensees Request for Alternative 3.1.1 ASME B&PV Code Components Affected Proposed alternative HC-I4R-190 applies to the RPV threads in flange Examination Category B-G-1, Item No. B6.40, in Section XI of the ASME B&PV Code.
Examination Examination Code Category Item No. Method Description Class B-G-1 B6.40 Volumetric RPV Threads in Flange 1 3.1.2 Applicable ASME B&PV Code Edition and Addenda For the fourth 10-year ISI interval at Hope Creek, the Code of Record for the inspection of ASME B&PV Code Class 1, 2, and 3 components is the 2007 Edition through the 2008 Addenda of the ASME B&PV Code, Section XI.
3.1.3 Applicable ASME B&PV Code Requirements and Proposed Alternative The applicable inspection requirement for this component is contained in Examination Category B-G-1, Item No. B6.40, which is listed in Table IWB-2500-1, Examination Categories, of the ASME B&PV Code, Section XI. This item requires volumetric examination, every ISI interval, of all the threads in RPV flange stud holes, as indicated in Figure IWB-2500-12, Closure Stud and Threads in Flange Stud Hole, of the ASME B&PV Code, Section XI.
The licensee proposes to eliminate the ASME B&PV Code requirement to volumetrically examine the threads in the RPV flange stud holes during the fourth ISI interval. Proposed alternative HC-I4R-190 is requested for the fourth ISI interval for Hope Creek. The fourth ISI interval for Hope Creek began on December 13, 2017, and is scheduled to end on December 31, 2026.
3.1.4 Licensees Technical Basis for Proposed Alternative The licensee states that the technical basis for eliminating the RPV threads in flange volumetric examinations is provided in Electric Power Research Institute (EPRI) Report No. 3002007626, Nondestructive Evaluation: Reactor Pressure Vessel Threads in Flange Examination Requirements (the EPRI report) (ADAMS Accession No. ML16221A068). The licensee discussed the potential degradation mechanisms, bounding stress analysis, flaw tolerance evaluation, and operating experience that were included in the EPRI report and concludes that these justify the elimination of volumetric examination of RPV threads. The licensee also states that the requirements in the relief request are based on ASME B&PV Code Case N-864, which has been approved by the ASME Board on Nuclear Codes and Standards. ASME B&PV Code Case N-864 states that the examination requirements of Examination Category B-G-1, Item Number B6.40, are not required.
Preload Stress Analysis The licensee performed a stress analysis specific to Hope Creek and compared the plant-specific preload stress to the bounding preload stress provided in the EPRI report. The licensee found that the preload stress for the Hope Creek units (calculated as 26,155 pounds per square inch (psi)) was bounded by the preload stress in the EPRI report (calculated as 42,338 psi).
Flaw Tolerance Evaluation The licensee stated that it used the acceptance criteria found in the ASME B&PV Code, Section XI, Article IWB-3610 and Appendix A, to compare the stress intensity factor (KI) for both preload and operating conditions with the fracture toughness based on crack initiation (KIC) using a structural factor of 10. The licensee assumed a preload temperature of 79 degrees Fahrenheit (°F) for the evaluations of preload only. For the evaluations of operating conditions, the licensee adopted the EPRI analysis which assumed an operating temperature of 600 °F.
For the preload only condition, the licensee used a maximum KI of 17.4 kilopound per square inch (ksi)inch, and a calculated KIC of 102 ksiinch. For the operating condition, the licensee used a maximum KI of 19.8 ksiinch and assumed a KIC of 220 ksiinch. The licensee stated that for both preload and operating conditions, KI < KIC/10, the allowable stress intensity factor is not exceeded for all crack depths up to the deepest analyzed flaw.
Maintenance and Inspection The licensee describes the maintenance activities and inspections that will be performed on the RPV threads in flange and studs each time the RPV head is removed. The licensee states that these controlled maintenance activities provide assurance that any degradation would be detected and mitigated prior to returning the reactor to service.
Finally, the licensee notes that the conclusion from the EPRI evaluation is that the safety benefit of the current examination requirements is not commensurate with the associated impact on worker exposure, personnel safety, generation of radwaste, critical path time, and additional time at reduced water inventory.
3.2 NRC Staff Evaluation The basis for proposed alternative HC-I4R-190 is provided in the EPRI report. By letter dated January 26, 2017 (ADAMS Accession No. ML17006A109), the NRC staff authorized Southern Nuclear Operating Company, Inc. (Southern Nuclear) to use a similar alternative that was based on the generic stress analysis and flaw tolerance evaluation in the EPRI report. The NRC staff's evaluation of the EPRI report is documented in Section 3.2.1, The EPRIs Generic Stress Analysis and Flaw Evaluation, of the Southern Nuclear safety evaluation. Section 3.2.1 of the Southern Nuclear safety evaluation concludes that the generic stress analysis and flaw tolerance evaluation in the EPRI report are acceptable, and the results can be used to support eliminating the RPV threads in flange examination. It should be noted that this conclusion was drawn in the context of authorizing the elimination of the volumetric inspection for a single 10-year ISI interval.
The NRC staff confirmed that the licensee performed the stress analysis consistent with the EPRI report. The NRC staff also verified the licensees calculation of preload stress at Hope Creek (26,155 psi) and verified that it was bounded by the preload stress in the EPRI report (42,338 psi).
The NRC staff confirmed that the licensee performed a linear elastic fracture mechanics evaluation consistent with the ASME B&PV Code, Section XI, IWB-3600, and the EPRI report.
The licensee assumed a maximum KI of 19.8 ksiinch for the operating condition (combined pressure, preload, and thermal stress), and a maximum KI of 17.4 ksiinch for the preload only condition, consistent with the EPRI report. For its evaluation of the operating condition, the licensee assumed a KIC of 220 ksiinch consistent with the assumptions of the EPRI report. For its evaluation of the preload only condition, the licensee calculated a KIC of 102 ksiinch based on the following equation in ASME B&PV Code, Section XI, Appendix A, Article A-4200:
KIC = 33.2 + 20.734 exp [0.2(T-RTNDT)] given that T=79 ºF and RTNDT=19 ºF For both preload and operating conditions, the licensee has demonstrated that KI < KIC/10 and the threads in the RPV flange are reasonably flaw tolerant.
The NRC staff reviewed the licensees description of the maintenance activities and inspections that will be performed on the RPV threads in flange and studs each time the RPV head is removed. The licensee stated that the RPV threads would be inspected when the studs are removed, cleaned, and lubricated. The NRC staff finds that the licensees maintenance activities provide an opportunity, at frequent intervals, for the licensee to detect and mitigate degradation of the threads in flange during the fourth ISI interval. These maintenance activities, combined with the linear elastic fracture mechanics evaluation discussed in the prior paragraph of this safety evaluation, provide a defense in depth to the possibility of component failure resulting from undetected and unmitigated cracking.
The NRC staff notes that the basis for the acceptability of the proposal is Code Case N-864, which the licensee correctly identified as being approved by the ASME B&PV Code and supported by a generic fatigue crack growth analysis contained in the EPRI report. The NRC staff also notes that some measure of defense in depth must be provided in the event of an alternate mode of failure. Therefore, in its review, the NRC staff focused on the adequacy of the generic fatigue crack growth analysis, the applicability of the generic analysis to the licensee, and the adequacy of the defense-in-depth measures proposed by the licensee.
In summary, the NRC staff has concluded that the stress analysis and flaw tolerance evaluation in the generic EPRI evaluation are bounding for Hope Creek.
4.0 CONCLUSION
As set forth above, the NRC staff determines that the licensee has demonstrated that the proposed alternative provides an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all the regulatory requirements set forth in 10 CFR 50.55a(z)(1) for the alternative request. Therefore, the NRC staff authorizes the use of alternative request HC-I4R-190 to eliminate the volumetric examination of the RPV threads in flange for the duration of the fourth 10-year ISI interval, which began on December 13, 2017, and is scheduled to end on December 31, 2026.
All other ASME B&PV Code, Section XI requirements for which relief was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: J. Jenkins Date: April 13, 2020