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MONTHYEARML19220A1022019-09-0606 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 Project stage: Other 2019-09-06
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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
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UNITED STATES WASHINGTON, D.C. 20555-0001 September 6, 2019 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 - ALTERNATIVE REQUEST VR-03 TO USE ASME CODE CASE OMN-17, ALTERNATIVE RULES FOR TESTING AMERICAN SOCIETY OF MECHANICAL ENGINEERS CLASS 1 PRESSURE RELIEF/SAFETY VALVES FOR THE FOURTH 10-YEAR INSERVICE TEST INTERVAL (EPID L-2019-LLR-0010)
Dear Mr. Carr:
By letter dated January 31, 2019 (Agencywide Documents and Access Management System (ADAMS) Accession Number ML190318845), PSEG Nuclear, LLC, (PSEG, the licensee),
submitted an alternative to the requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), associated with valve inservice testing (1ST) at the Hope Creek Generating Station (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 request VR-03 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 concluded that for alternative request VR-03 for Hope Creek, the proposed alternative provides an acceptable level of quality and safety for the Main Steam and Automatic Depressurization System Valves. 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 request VR-03.
Therefore, the NRC staff authorizes the use of the alternative request VR-03 for Hope Creek for the duration of the fourth 10-year 1ST program interval, which began on December 21, 2017, and is scheduled to end on December 20, 2026 (Hope Creek extended the third 10-year 1ST program interval by one year, therefore the fourth 10-year 1ST program interval began on December 21, 2017).
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 =-'-'-"-.::::..:..:...:.:.:..:..:.==..;;i..;;:;...;;..*
Sincerely, CJ~
J~s 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
UNITED STATES WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION ALTERNATIVE REQUEST VR-03 FOR FOURTH 10-YEAR INTERVAL INSERVICE TESTING PROGRAM HOPE CREEK GENERATING STATION EXELON GENERATION COMPANY. LLC DOCKET NO. 50-354
1.0 INTRODUCTION
By letter dated January 31, 2019 (Agencywide Documents and Access Management System (ADAMS) Accession Number ML190318845), PSEG Nuclear, LLC, (the licensee), submitted an alternative to the requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), associated with valve inservice testing (1ST) at the Hope Creek Generating Station (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 request VR-03 on the basis that the alternative provides an acceptable level of quality and safety.
2.0 REGULATORY EVALUATION
As stated under 10 CFR 50.55a(f), in part, that 1ST of certain ASME Code Class 1, 2, and 3 pumps and valves are to be performed in accordance with the specified ASME OM Code and applicable addenda incorporated by reference in the regulations.
As stated under 10 CFR 50.55a(z), alternatives to the requirements of paragraph (f) of 10 CFR 50.55a may be used, when authorized by the U.S. Nuclear Regulatory Commission (NRC), if the licensee demonstrates: ( 1) the proposed alternatives would provide an acceptable level of quality and safety or (2) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
3.0 TECHNICAL EVALUATION
3.1 Licensee's Alternative Request VR-03 The licensee requested to implement Code Case OMN-17 as an alternative to the valve testing requirements of the ASME OM Code.
Enclosure
ISTA-3130, "Application of Code Cases," (b}, states, "Code Cases shall be applicable to the edition and addenda specified in the test plan."
1-1320, "Test Frequencies, Class 1 Pressure Relief Valves," (a) "5-Yr Test Interval," states, "Class 1 pressure relief valves shall be tested at least once every 5 year, starting with initial electric power generation. No maximum limit is specified for the number of valves to be tested within each interval; however, a minimum of 20% of the valves from each valve group shall be tested within any 24-mo interval. This 20% shall consist of valves that have not been tested during the current 5-yr interval, if they exist. The test interval for any installed valve shall not exceed 5 yr. The 5-yr test interval shall begin from the date of the as-left set pressure test for each valve."
1-3310, "Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices," states, "Tests before maintenance or set-pressure adjustment, or both, shall be performed for subparagraphs. 1-331 O(a) through (c) in sequence. The remaining shall be performed after maintenance or set-pressure adjustments.
(a) visual examination (b) seat tightness determination, if practicable (c) set-pressure determination (d) determination of electrical characteristics and pressure integrity of solenoid valve(s)
(e) determination of pressure integrity and stroke capability of air actuator (f) determination of operation and electrical characteristics of position indicators (g) determination of operation and electrical characteristics of bellows alarm switch (h) determination of actuating pressure of auxiliary actuating device sensing element, where applicable, and electrical continuity (i) determination of compliance with the Owner's seat tightness criteria" l-1320(a), "5-Yr Test Interval," states, "Class 1 pressure relief valves shall be tested at least once every 5 year, starting with initial electric power generation. No maximum limit is specified for the number of valves to be tested within each interval; however, a minimum of 20% of the valves from each valve group shall be tested within any 24-mo interval. This 20% shall consist of valves that have not been tested during the current 5-yr interval, if they exist. The test interval for any installed valve shall not exceed 5 yr. The 5-yr test interval shall begin from the date of the as-left set pressure test for each valve.
The licensee has requested to use the proposed alternative described below the following valves:
Main Steam and Automatic Depressurization System (ADS) Valves:
1SNPSV-F013A, B, C, D, E (Class 1, Category C) 1ABPSV-F013F, G, H, J, K, L, M, P, R (Class 1, Category C)
The Hope Creek fourth 10-year 1ST program interval began on December 21, 2017, and is scheduled to end on December 20, 2026. The applicable ASME OM Code edition for the Hope Creek fourth 10-year 1ST program interval is the 2012 Edition.
Reason for Request
The licensee stated:
These valves [listed above] have a safety function in the open position to provide overpressure protection for the main steam header and the reactor vessel.
Additionally, valves 1SNPSV.:.F013A-E also serve an emergency core cooling system (ECCS) function in the ADS to depressurize the reactor vessel in the event of a small break loss-of-coolant accident (LOCA) coincident with a failure of the high pressure coolant injection (HPCI) system.
The ASME OM Committee developed Code Case OMN-17, Alternative Rules for Testing ASME Class 1 Pressure Relief/Safety Valves, which is published in the 2012 Edition of the OM Code. Regulatory Guide (RG) 1.192, "Operation and Maintenance Code Case Acceptability, ASME OM Code," Revision 2, Table 1 identifies Code Case OMN-17 as an acceptable Code Case for implementation in the in-service testing program. However, the inquiry and reply within Code Case OMN-17 indicate that its applicability to the OM Code is to the 2001 Edition through the 2006 Addenda of Appendix I, Section 1-1320. ISTA-3130(b) requires Code Cases to be applicable to the Edition and addenda specified in the test plan, which would be the 2012 Edition. Therefore, NRC authorization is needed
.to use Code Case OMN-17 for testing of the subject relief valves.
Proposed Alternative The licensee stated:
As an alternative to the Code required five-year test interval per Appendix I, paragraph 1-1320(a), PSEG proposes that the subject Class 1 pressure relief valves be tested at least once every 72 months with a minimum of 20% of the valves tested within any 24-month interval. This 20% would consist of valves that have not been tested during the current three-cycle interval, if they exist. The test interval for any individual valve would not exceed 72 months, except that a 6-month grace period is allowed to coincide with refueling outages to accommodate extended shutdown periods. Prior to placing these valves in service, the valves shall be disassembled and inspected after as-found set- pressure testing to verify that parts are free of defects resulting from time-related degradation or service-induced wear. As-left set-pressure testing shall be performed following maintenance and prior to returning the valve to service. Each valve shall have been disassembled and inspected at least once during the 72-month test interval.
Disassembly and inspections performed prior to the implementation of this alternative may be used.
Relief from ISTA-3130(b) is requested to implement Code Case OMN-17, since inquiry and reply within the Code Case indicates that its applicability is to the 2001 Edition through the 2006 Addenda of Appendix I. ISTA-3130(b) requires Code Cases to be applicable to the Edition and addenda specified in the test plan. The ASME OM Code that applies to the Hope Creek test plan is the 2012 Edition with no Addenda. A review of the 2012 Edition of the OM Code and Code Case OMN-17 confirmed that there are no changes that would affect use of
this Code Case relative to the applicable Code section referenced within the Code Case when comparing Appendix I of the 2001 Edition through the 2006 Addenda to Appendix I of the 2012 Edition.
The proposed alternative of increasing the test interval for the subject Class 1 pressure relief valves from five years to 72 months would continue to provide an acceptable level of quality and safety. This proposed alternative meets the requirements stated in Code Case OMN-17, which is approved for use in RG 1.192, Revision 2. The proposed alternative will continue to provide assurance of the valves' operational readiness and provides an acceptable level of quality and safety pursuant to 10 CFR 50.55a(z)(1 ).
NRC Staff's Evaluation The application of ASME OM Code Cases is addressed in 10 CFR 50.55a(b)(6) through references to RG 1.192, Revision 2, which lists acceptable and conditionally acceptable code cases for implementation in the 1ST program and Snubber program. Table 1 in RG 1.192, Revision 2 shows that Code Case OMN-17 is approved for use. However, its use in conjunction with the 2012 Edition of the ASME OM Code (Hope Creek code of reference) is still precluded by the applicability language in the code case itself, which limits its use to OM Code editions and addenda up to and including the 2006 Addenda. Nonetheless, the NRC has allowed licensees to use OMN-17 with later OM Code editions, provided all requirements in the code case are met. Consistent with the special maintenance requirement in ASME OM Code Case OMN-17, each Main Steam and ADS valve at Hope Creek listed above is disassembled and inspected to verify that internal surfaces and parts are free from defects resulting from time-related degradation or service-induced wear prior to the start of the next test interval. During this process, anomalies or damage are identified for resolution. Damaged or worn parts, springs, gaskets, and seals are replaced as necessary. The purpose of this maintenance requirement is to reduce the potential for pressure relief valve set-point drift. Following reassembly, the valve's set pressure is recertified. This existing process is in accordance with ASME OM Code Case OMN-17, paragraphs (d) and (e).
Furthermore, ASME OM Code Case OMN-17 is performance-based in that it requires that the valves be tested more frequently if test failures occur. For example, ASME OM Code Case OMN-17 requires that two additional valves be tested when a valve in the initial test group exceeds the set pressure acceptance criteria. All remaining valves in the group are required to be tested if one of the additional valves tested exceeds its set pressure acceptance criteria.
The NRC staff reviewed the 2012 Edition of the ASME OM Code and Code Case OMN-17 and confirmed that there are no changes in the applicable Code sections referenced within the Code Case OMN-17. Therefore, there is no technical reason for prohibiting the use of Code Case OMN-17 with the 2012 Edition of the ASME OM Code. Based on the disassembly and inspection of the valves after as-found set-pressure testing and prior to use, the NRC staff finds that implementation of ASME OM Code Case OMN-17 for the testing of the designated valves listed above, in lieu of the requirements of the 2012 Edition of the ASME OM Code, and the requirements of Mandatory Appendix I, Section 1-1320, of the ASME OM Code, provides an acceptable level of quality and safety.
4.0 CONCLUSION
As set forth above, the NRC staff determined that for alternative request VR-03 for Hope Creek, the proposed alternative provides an acceptable level of quality and safety for the Main Steam and ADS Valves listed above. 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 request VR-03. Therefore, the NRC staff authorizes the use of the alternative request VR-03 for Hope Creek for duration of the fourth 10-year 1ST program interval, which began on December 21, 2017, and is scheduled to end on December 20, 2026 (Hope Creek extended the third 10-year 1ST program interval by one year, such that the fourth 10-year 1ST program interval began on December 21, 2017).
All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject requests remain applicable.
Principal Contributor: R. Wolfgang Date: September 6, 2019
E. Carr
SUBJECT:
HOPE CREEK NUCLEAR GENERATING STATION-ALTERNATIVE REQUEST VR-03 TO USE ASME CODE CASE OMN-17, ALTERNATIVE RULES FOR TESTING ASME CLASS 1 PRESSURE RELIEF/SAFETY VALVES FOR THE FOURTH 10-YEAR INSERVICE TEST INTERVAL (EPID L-2019-LLR-0010) DATED SEPTEMBER 6, 2019 DISTRIBUTION:
PUBLIC PM File Copy RidsNrrDorlLpl1 Resource RidsNrrPMHopeCreek Resource RidsNrrLACSmith Resource RidsNrrDeEmib Resource RidsACRS_MailCTR Resource RidsRgn1 MailCenter Resource RWolfgang, NRR DDodson, OEDO ADAMS Access1on No.: ML19220A102 *biv e-ma1*1 OFFICE NRR/DORL/LPL 1 :PM NRR/DORL/LPL 1 :LA NRR/DE/EMIB:BC* NRR/DORL/LPL 1:BC NAME JKim CSmith SBailey JDanna DATE 08/20/19 08/20/19 08/01/19 09/06/19 OFFICIAL RECORD COPY