Similar Documents at Salem |
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Category:Letter
MONTHYEARIR 05000272/20230042024-02-0505 February 2024 Integrated Inspection Report 05000272/2023004 and 05000311/2023004 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 ML24004A1542024-01-0808 January 2024 Notification of Conduct of a Fire Protection Team Inspection 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 ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement 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 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 LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 IR 05000272/20230102023-10-12012 October 2023 Biennial Problem Identification and Resolution Inspection Report O5000272/2023010 and 05000311/2023010 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-N23-0045, 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) 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 LR-N23-0054, In-Service Inspection Activities2023-07-26026 July 2023 In-Service Inspection Activities 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 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) LR-N23-0033, Core Operating Limits Report Cycle 272023-04-26026 April 2023 Core Operating Limits Report Cycle 27 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 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 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 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-N23-0006, 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 RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations 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 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 IR 05000272/20230112023-03-0707 March 2023 Comprehensive Engineering Team Inspection Report 05000272/2023011 and 05000311/2023011 IR 05000272/20220062023-03-0101 March 2023 Annual Assessment Letter for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2022006 and 05000311/2022006) 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-N23-0012, 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 ML23034A1532023-02-0909 February 2023 Operator Licensing Examination Approval ML23019A3482023-02-0202 February 2023 Issuance of Relief Request No. SC-I5R-221 for the Alternative Repair for Service Water System Piping LR-N23-0003, Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-2112023-02-0101 February 2023 Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-211 2024-02-05
[Table view] Category:Safety Evaluation
MONTHYEARML23192A8212023-08-14014 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 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 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 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 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 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 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 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 ML19077A3362019-04-11011 April 2019 Issuance of Amendment Nos. 328 and 309 Revise Technical Specifications to Extend Refueling Water Storage Tank Allowed Outage Time 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 ML19050A3702019-03-0606 March 2019 Alternative to Reactor Vessel Nozzle Welds Examinations Inspection Interval (EPID-L-2018-LLR-0110) ML19009A4772019-01-25025 January 2019 Issuance of Amendment Nos. 326 and 307 Revise Technical Specifications to Increase Vital Instrument Bus Inverter Allowed Outage Time ML18318A2662018-12-19019 December 2018 Issuance of Amendment Nos. 325 and 306 Revise TS Reactor Trip System Instrumentation and Engineered Safety Features Actuation System Instrumentation Test Times and Completion Times ML18142B1262018-05-29029 May 2018 Use of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Inservice Inspection Activities ML18040A7782018-04-18018 April 2018 Issuance of Amendment Nos. 323 and 304 Relocation of Reactor Coolant System Pressure Isolation Valve Tables ML18085B1982018-04-18018 April 2018 Issuance of Amendment Nos. 324 and 305 Revise Technical Specification Actions for Rod Position Indicators 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) ML17349A1082018-01-18018 January 2018 Issuance of Amendments Containment Fan Coil Unit Allowed Outage Time Extension (CAC Nos. MF9364 and MF9365; EPID L-2017-LLA-0212) ML17227A0162017-11-14014 November 2017 Issuance of Amendments Accident Monitoring Instrumentation ML17304A9432017-11-0101 November 2017 Use of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Inservice Inspection Activities ML17219A1862017-08-17017 August 2017 Safety Evaluation of Relief Request SC-I4R-171 Regarding the Fourth 10-Year Interval of the Inservice Inspection Program ML17172A5872017-07-17017 July 2017 Safety Evaluation of Relief Request S1-I4R-160 Regarding the Fourth 10-Year Interval of the Inservice Inspection Program ML17165A2142017-06-28028 June 2017 Issuance of Amendment to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule App. to Section 5.5 Testing ML17132A0052017-05-19019 May 2017 Alternative Request to Adopt American Society of Mechanical Engineers Code Case OMN-20 (CAC Nos. MF8313 and MF8314) 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 ML17012A2922017-02-0606 February 2017 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Issuance of Amendments ML16351A1822017-01-19019 January 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16229A5192016-09-29029 September 2016 Issuance of Amendments Correct Non-Conservative Technical Specifications and Other Discrepancies ML16137A5792016-06-29029 June 2016 Issuance of Amendments Extension of Implementation Period for Salem, Unit No. 1, License Amendment No. 311, and Salem, Unit No. 2 License Amendment No. 292 2023-08-14
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 17, 2017 Mr. Peter P. Sena, Ill President and Chief Nuclear Officer PSEG Nuclear LLC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 -SAFETY EVALUATION OF RELIEF REQUEST S1-14R-160 REGARDING THE FOURTH 10-YEAR INTERVAL OF THE INSERVICE INSPECTION PROGRAM (CAC NO. MF9149)
Dear Mr. Sena:
By letter dated January 31, 2017, PSEG Nuclear LLC (PSEG, the licensee) submitted Relief Request S1-14R-160 to the U.S. Nuclear Regulatory Commission (NRC). PSEG proposed an alternative to certain inservice inspection requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) for Salem Nuclear Generating Station (Salem), Unit No. 1. Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 O CFR) 50.55a(z)(2), PSEG requested to extend the required reactor pressure vessel cold leg nozzle inspections by approximately 6 months (until the spring 2019 refueling outage). The subject relief request is for the fourth 10-year interval of the inservice inspection program at Salem Unit No. 1, which began on May 20, 2011, and is currently scheduled to end on December 31, 2020.
The NRC staff has completed its review of the subject relief request as documented in the enclosed safety evaluation. Our safety evaluation concludes that the proposed alternative provides reasonable assurance of the structural integrity of the subject components, and that complying with the ASME Code requirements would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 1O CFR 50.55a(z)(2). Therefore, the NRC staff authorizes the use of the proposed alternative, for Salem, Unit No. 1, until startup from the spring 2019 refueling outage (S1 R26).
All other ASME Code,Section XI requirements for which relief was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
P.Sena If you have any questions concerning this matter, please contact the Salem Project Manager, Mr. Richard Ennis, at (301) 415-1420 or Rick.Ennis@nrc.gov.
Sincerely, Cfiv~""'uj'-"'~c--
James G. Danna, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-272
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO RELIEF REQUEST S1-14R-160 FOURTH 10-YEAR INTERVAL OF THE INSERVICE INSPECTION PROGRAM PSEG NUCLEAR LLC SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 DOCKET NO. 50-272
1.0 INTRODUCTION
By letter dated January 31, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17031A278), PSEG Nuclear LLC (PSEG, the licensee) submitted Relief Request S1-14R-160 to the U.S. Nuclear Regulatory Commission (NRC). PSEG proposed an alternative to certain inservice inspection (ISi) requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) for Salem Nuclear Generating Station (Salem), Unit No. 1. Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 O CFR) 50.55a(z)(2), PSEG requested to extend the required reactor pressure vessel (RPV) cold leg nozzle inspections by approximately 6 months (until the spring 2019 refueling outage). The subject relief request is for the fourth 10-year interval of the ISi program at Salem, Unit No. 1, which began on May 20, 2011, and is currently scheduled to end on December 31, 2020.
2.0 REGULATORY EVALUATION
In this relief request, the licensee proposes to use an alternative inspection frequency to the requirements of Table 1 of ASME Code Case N-770-1 as referenced in 10 CFR 50.55a(g)(6)(ii)(F).
Pursuant to 10 CFR 50.55a(g)(4), throughout the service life of a boiling or pressurized water-cooled nuclear power facility, components that are classified ASME Code Class 1, 2, and 3 must meet the requirements, except the design and access provisions and preservice examination requirements, set forth in the ASME Code,Section XI, to the extent practical, within the limitations of design, geometry, and materials of construction of the components. Further, these regulations require that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in paragraph (a) of 1O CFR 50.55a on the date 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein.
Enclosure
Alternatives to requirements under 1O CFR 50.55a(g) may be authorized by the NRC pursuant to 10 CFR 50.55a(z)(1) or 1O CFR 50.55a(z)(2). In proposing alternatives or requests for relief, the licensee must demonstrate that: (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 Commission to authorize the proposed alternative requested by the licensee. Accordingly, the NRC staff has reviewed and evaluated the licensee's request pursuant to 10 CFR 50.55a(z)(2).
3.0 TECHNICAL EVALUATION
3.1 Licensee Relief Request S1-14R-160 3.1.1 Component Identification The proposed alternative applies to the four RPV cold leg nozzle to safe-end alloy 600 butt welds, numbered as follows:
Loop 11 - 27.5-RC-1110-5 Loop 12 - 27.5-RC-1120-5 Loop 13 - 27.5-RC-1130-5 Loop 14 - 27.5-RC-1140-5 3.1.2 Applicable Code Edition and Addenda The applicable ASME Code of Record for the fourth 10-year ISi interval, for Salem, Unit No. 1, is the 2004 Edition with no Addenda.
3.1.3 Code Requirements for Which Relief is Requested As discussed in 1O CFR 50.55a(g)(6)(ii)(F), licensees of existing, operating pressurized-water reactors (PWRs) as of July 21, 2011, must implement the requirements of ASME Code Case N-770-1, subject to the conditions specified in paragraphs (g)(6)(ii)(F)(2) through (10) of 10 CFR 50.SSa. Table 1 of ASME Code Case N-770-1, in part, establishes the inspection frequency of the RPV inlet dissimilar metal butt welds. These welds at Salem, Unit No. 1, are categorized as Inspection Item D welds, which have been mitigated with the Mechanical Stress Improvement Process (MSIP) with no previous indication of cracking. Paragraph (g)(6)(ii)(F)(9) of 1O CFR 50.55a states the following regarding Inspection Item D welds:
Replace the first two sentences of Extent and Frequency of Examination for Inspection Item Din Table 1 of Code Case N-770-1 with, "Examine all welds no sooner than the third refueling outage and no later than 10 years following stress improvement application." Replace the first two sentences of Note (11 )(b)(2) in Code Case N-770-1 with, "The first examination following weld inlay, onlay, weld overlay, or stress improvement for Inspection Items D through K must be performed as specified."
Therefore, the inspection frequency for the first followup examination following the application of the MSI P process is no sooner than the third refueling outage, and no later than 1O years
following the application of the MSIP. The licensee stated that the MSIP application was performed in the fall 2008 refueling outage. Therefore, the RPV cold leg nozzle to safe-end welds volumetric examinations are currently required to be completed by fall 2018. This would require the examinations to be completed during the Salem, Unit No. 1, fall 2017 refueling outage (S1 R25) since the S1 R26 refueling outage in the spring of 2019 would be 6 months beyond the 10-year inspection interval.
3.1 .4 Licensee's Proposed Alternative PSEG requested a one-time 6-month extension to the 10-year volumetric examination interval required by Table 1 of Code Case N-770-1, as conditioned by 1O CFR 50.55a(g)(6)(ii)(F)(9), for Item D (uncracked butt welds mitigated with stress improvement). The 6-month extension to the 10-year examination interval would allow the four RPV cold leg nozzle to safe-end weld examinations to be performed during the Salem, Unit No. 1, spring 2019 refueling outage (S1 R26).
This interval extension is being requested in accordance with 1O CFR 50.55a(z)(2) as a hardship, without a compensating increase in quality and safety.
3.1.5 Licensee's Duration of Relief Request The duration for the proposed alternative is through the spring 2019 refueling outage (S1 R26).
3.1.6 Licensee's Basis for Relief As discussed above in Section 3.1.3, without the relief request, the examinations would be required to be completed during the Salem, Unit No. 1, fall 2017 refueling outage (S1 R25),
since the S1 R26 refueling outage in the spring of 2019 would be 6 months beyond the required 10-year inspection interval.
The licensee stated that during refueling outage S1 R26, examinations in accordance with the Reactor Vessel Internals Materials Reliability Program (MRP-227) and other scheduled ASME Section XI RPV examinations will require removal of the core barrel and, therefore, provide access for remote volumetric examinations of the RPV cold leg nozzle to safe-end welds from the inside surface of the pipe. The licensee further stated that performance of the RPV cold leg nozzle to safe-end welds examinations during refueling outage 81 R25 would require the examinations to be performed from the outside surface of the pipe.
Due to the location of the welds, the licensee estimated that the volumetric inspections during S1 R25 would cause a radiological dose exposure of approximately 3.5 roentgen equivalent man (rem). PSEG stated that performing the inspections from the inside surface of the pipe during S1 R26 would reduce the overall exposure of the weld examinations since the inspection technique is performed remotely. The licensee stated that performing the examinations during S1 R25 would result in unnecessary personnel radiation exposure, without a compensating increase in quality or safety.
PSEG cited information to show that a 6-month delay in the volumetric inspection requirement would continue to provide an adequate level of quality and safety. The licensee noted that NUREG/CR-7187, "Managing PWSCC in Butt Welds by Mitigation and Inspection," published November 2014 (ADAMS Accession No. ML14329A085), states that "it is reasonable to conclude that MSIP provides effective mitigation against the initiation of PWSCC and against
the growth of any existing PWSCC that has been detected and allowed to remain in service."
As all of the subject welds have been mitigated with MSIP and were previously found to have no indications of cracking, the licensee also stated that the volumetric examinations were considered more of a defense-in-depth monitoring measure and not for management of primary water stress corrosion cracking (PWSCC) degradation. The licensee cited information in Section 4.5 of NUREG/CR-7187, which supports this position.
In summary, PSEG believes that imposition of the 10-year inspection requirement would create a hardship in that personnel would unnecessarily receive additional radiation exposure, in the order of 3.5 rem, if the volumetric examinations were performed during the fall 2017 refueling outage, without an increase in quality or safety. As such, the licensee requested that the inspection of the four RPV cold leg nozzle to safe-end welds be performed during the spring 2019 refueling outage.
3.2 NRC Staff's Evaluation The NRC staff has reviewed and evaluated the licensee's request on the basis that compliance with the specified requirements would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety. The NRC staff finds that the licensee's identified hardship of the radiological dose of approximately 3.5 rem is technically reasonable. If an outside diameter examination is performed, the examination and required equipment setup, including scaffolding and temporary shielding, would be in a radiation area next to the RPV.
Further, the estimated radiological dose is based on previous examinations performed at Salem, Unit No. 1, rather than a simple assessment. Therefore, the NRC staff finds that the licensee has demonstrated a hardship in performing the volumetric examinations from the outside versus the inside surface.
The NRC staff reviewed the quality and safety impact of the licensee's proposed alternative to allow a 6-month delay in the volumetric examination, beyond the current regulatory requirement of 10 years. The NRC staff finds that the volumetric inspections of the subject welds can be performed with qualified methods, both from the outside and inside surfaces of the welds, so there is no reduction in inspection quality.
From a safety perspective, the NRC staff notes that the degradation mechanism of concern is PWSCC. The MSIP mitigation technique, when effectively implemented, prevents new flaw initiation and growth of existing shallow flaws by removing the tensile stress necessary for both.
The NRC staff notes that after hundreds of applications of the MSIP process in U.S. nuclear power plants, no MSIP mitigated weld has identified leakage or a structurally significant flaw.
Additionally, PWSCC initiation and flaw growth is significantly affected by temperature, typically by a factor of 5, between the average hot leg and cold leg temperatures at a PWR. Further, the NRC staff acknowledges that no significant cracking has been identified in similar sized cold leg temperature welds at any U.S. PWR. Therefore, the NRC staff finds it is unlikely that a flaw would have initiated, or if it had, would grow, to a size to challenge structural integrity during the period of inspection frequency extension.
The purpose of the initial inspection following the application of MSIP is as a defense-in-depth inspection to verify the effectiveness of the application of the MSIP on each weld. This is a one-time inspection. Once completed, and if no flaws or growth of existing flaws is verified, the volumetric inspection requirement is a 25 percent sample of all MSIP mitigated welds each 10-year ISi period. The purpose of the NRC condition in 10 CFR 50.55a(g)(6)(ii)(F)(9) for MSIP mitigated welds is to ensure that sufficient time has transpired to allow initiation or growth of any
existing flaws and to prevent the first volumetric examination from being deferred to possibly 20 years. The NRC staff finds that the licensee's proposed extension of only 6 months does not challenge the technical basis of the time period for effectiveness of the first volumetric examination after MSIP application. Further, the NRC staff notes that this is not the only method of assurance. Plant walkdowns and plant leakage monitoring systems also provide defense-in-depth measures. Therefore, the NRC staff finds that the licensee's proposed alternative has an insignificant, if any, impact on safety.
Given the licensee's identified hardship and the NRC staff's assessment of the volumetric inspection frequency extension of 6 months, the NRC finds that the licensee's proposed alternative is acceptable on the basis that compliance with the specified requirements would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety.
4.0 CONCLUSION
As set forth above, the NRC staff determines that the proposed alternative provides reasonable assurance of the structural integrity of the subject components, and that complying with the ASME Code requirements would result in hardship or unusual difficulty, without a compensating increase in the level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(2). Therefore, the NRC staff authorizes the use of the proposed alternative for Salem, Unit No. 1, until startup from the spring 2019 refueling outage (S1 R26).
All other ASME Code,Section XI requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
Principal Contributors: J. Collins R. Ennis Date: July 17, 2017
ML17172A587 OFFICE DORL/LPL 1/PM DORL/LPL 1/LA DE/EPNB/BC DORL/LPL 1/BC DORL/LPL 1/PM NAME REnnis LRonewicz DAiiey JDanna REnnis DATE 07/06/2017 06/22/2017 07/06/2017 07/12/2017 07/17/2017