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Category:Code Relief or Alternative
MONTHYEARML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML23262B4442023-09-26026 September 2023 Authorization and Safety Evaluation for Alternative Request No. I4R-14 ML22194A9152022-07-15015 July 2022 Proposed Alternative I4-R13 for Repair of Recirculation Flow Control Valves RS-22-032, Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs2022-03-0202 March 2022 Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20099D9552020-04-17017 April 2020 Request to Use Provisions in the 2013 Edition of the ASME Boiler and Pressure Vessel Code for Performing Non-Destructive Examinations ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques RS-19-066, Relief Request RV-03 Related to Pressure Isolation Valve Testing Frequency2019-06-28028 June 2019 Relief Request RV-03 Related to Pressure Isolation Valve Testing Frequency ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19121A3172019-05-20020 May 2019 Relief Request 13R-15, Relief from the Requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&Pv) Code, Section X1, Rules for Inservice Inspection (EPID-L-2018-LLR-0123) ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins JAFP-19-0023, Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds2019-02-15015 February 2019 Relief Request Associated with the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Piping Welds RS-18-112, End of Interval Relief Request Associated with the Third Ten-Year Inservice Inspection (ISI) Interval2018-09-19019 September 2018 End of Interval Relief Request Associated with the Third Ten-Year Inservice Inspection (ISI) Interval JAFP-18-0052, Proposed Alternative to Utilize Code Case N-8792018-05-30030 May 2018 Proposed Alternative to Utilize Code Case N-879 JAFP-18-0053, Proposed Alternative to Utilize Code Cases N-878 and N-8802018-05-30030 May 2018 Proposed Alternative to Utilize Code Cases N-878 and N-880 ML18011B1112018-01-23023 January 2018 Relief from the Requirements of the ASME Code and OM Code Relief Requests I4R-04, Proposed Alternatives to Various Inservice Inspection Interval (ISI) Requirements of the American Society of Mechanical Engineers, Section XI, 2007 Edition ML18003A2472018-01-0808 January 2018 Relief from the Requirements of the ASME Code and OM Code Relief Requests I4R-01 (CAC Nos. MF9758 and MF9759; EPID L-2017-LLR-0057) ML17354A8542018-01-0303 January 2018 Approval of Alternative to the ASME Code Regarding Inspection of Hydrogen Recombiner System Piping - Relief Request I4R-08 (CAC Nos. MF9772 and MF9773; EPID L-2017-LLR-0036) RA17-086, County Station, Units I & 2 - 10CFR50.55a Relief Request 14R-012017-11-10010 November 2017 County Station, Units I & 2 - 10CFR50.55a Relief Request 14R-01 ML17261A0782017-10-12012 October 2017 Request for Additional Information Regarding Relief Request I4R-01 (CAC Nos. MF9758 and MF9759; EPID L-2017-LLR-0057) ML17171A3202017-07-0505 July 2017 Relief from the Requirements of the ASME Code Regarding Relief Request I4-R-10, Proposed Alternative to Utilize Code Case N-513-4 ML17170A0132017-06-26026 June 2017 Proposed Alternative to Eliminate Examination of Threads in Reactor Pressure Vessel Flange (CAC Nos. MF8712-MF8729 and MF9548) ML17059C5832017-03-0101 March 2017 Relief from ASME Code for OM Code Re. RR RV-01 Proposed Alternative to Inservice Testing Requirement of ASME Code for OM Code ML17024A2652017-02-22022 February 2017 Letter to Licensee, Approvals of Relief Requests-G-01, RP-01, and RP-04 for the Fourth 10-Year Inservice Testing Intervals (MF8490, MF8491, MF8492, MF8493, MF8498, and MF8499) ML17047A5862017-02-22022 February 2017 Letter to Licensee, Approvals of Relief Requests-RP-02, and RP-03 for the Fourth 10-Year Inservice Testing Intervals (CAC Nos. MF8494 - MF8497) ML16230A2372016-09-0606 September 2016 Fleet Request for Proposed Alternative to Use ASME Code Case N-513-4 (CAC Nos. MF7301-MF7322) ML15226A4122015-10-30030 October 2015 MF5654 & MF5655, Letter to Licensee -Authorization of RR-I3R14 (MF5654 & MF5655-Lasalle RRI3R14(08-14-2015) ML12121A6372012-05-10010 May 2012 Request to Use Code Case N-789 ML0925703212009-09-21021 September 2009 Relief Request CR-26, Inservice Inspection Program Relief Regarding Examination Coverage for the Second 10-Year Inservice Inspection Interval, MD9817 - MD9818 ML0809301222008-05-0707 May 2008 Request for Relief from ASME OM Code for the Third Inservice Testing Interval ML0809803112008-04-30030 April 2008 Relief Request to Use Boiling Water Reactor Vessel & Internals Project Guidelines.. ML0736105872008-01-30030 January 2008 Request for Relief Nos. I3R-03, I3R-04, I3R-08, I3R-09 and I3R-10: Third 10-Year Interval Inservice Inspection Program Plan ML0333001472004-01-28028 January 2004 Relief Request, Shell Weld Inspection, TAC No MB9755 and MB9756 ML0219800132002-07-29029 July 2002 Code Relief, Relief Request RV-13 to Delay Sr/V Setpoint Testing 2023-09-26
[Table view] Category:Letter
MONTHYEARIR 05000373/20230042024-01-24024 January 2024 County Station - Integrated Inspection Report 05000373/2023004 and 05000374/2023004 ML24024A1332024-01-24024 January 2024 Confirmation of Initial License Examination IR 05000373/20230122024-01-18018 January 2024 County Station - Biennial Problem Identification and Resolution Inspection Report 05000373/2023012 and 05000374/2023012 ML23354A2902024-01-0505 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0028 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23360A6082023-12-27027 December 2023 County Station Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000373/2024010 and 05000374/2024010 ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information IR 05000373/20230032023-11-0909 November 2023 County Station Integrated Inspection Report 05000373/2023003, 05000374/2023003, and 07200070/2023001 ML23286A2602023-11-0808 November 2023 Issuance of Amendment Nos. 260 and 245 to Renewed Facility Operating Licenses Relocation of Pressure and Temperature Limit Curves to the Pressure Temperature Report IR 05000373/20234012023-11-0707 November 2023 County Station Security Baseline Inspection Report 05000373/2023401 and 05000374/2023401 RS-23-103, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans IR 05000374/20230102023-10-11011 October 2023 NRC Inspection Report 05000374/2023010 IR 05000373/20233012023-09-15015 September 2023 Errata to NRC Initial License Examination Report 05000373/2023301; 05000374/2023301 RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor ML23212A9012023-08-0303 August 2023 Regulatory Audit Report to Support the Review of the Amendments to Relocation of the Pressure Temperature Limit Curves to the Pressure and Temperature Limits Report IR 05000373/20230022023-08-0101 August 2023 County Station - Integrated Inspection Report 05000373/2023002 and 05000374/2023002 ML23208A3182023-07-27027 July 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI RS-23-084, Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-07-24024 July 2023 Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis ML23192A5272023-07-12012 July 2023 NRC Initial License Examination Report 05000373/2023301; 05000374/2023301 ML23186A2062023-07-0606 July 2023 Information Request for a NRC Post-Approval Site Inspection for License Renewal 05000374/2023010 ML23181A1502023-06-30030 June 2023 Combined Response to Request for Additional Information and Supplemental Information in Support of LAR to Relocate Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III IR 05000373/20230112023-06-26026 June 2023 County Station - Quadrennial Fire Protection Team Inspection Report 05000373/2023011 and 05000374/2023011 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23167A0352023-06-16016 June 2023 Registration of Use of Cask to Store Spent Fuel ML23171A9562023-06-12012 June 2023 Post Exam Ltr RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000373/20230012023-05-10010 May 2023 County Station - Integrated Inspection Report 05000373/2023001 and 05000374/2023001 ML23123A2202023-05-0303 May 2023 Relief Request I4R-14 for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23121A1612023-05-0101 May 2023 Information Meeting (Open House) with a Question-and-Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of LaSalle County Station, Units 1 and 2 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23107A1822023-04-18018 April 2023 Operator Licensing Examination Approval Lasalle County Station, May 2023 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 ML23073A2182023-03-22022 March 2023 Issuance of Amendment No. 258 to Renewed Facility Operating Licenses Exigent Amendment to Revise Design Basis Related to Seismic Requirements RS-23-048, Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements2023-03-0707 March 2023 Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 IR 05000373/20220062023-03-0101 March 2023 Annual Assessment Letter for LaSalle County Station, Units 1 and 2 (Report 05000373/2022006 and 05000374/2022006) RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-037, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station2023-02-22022 February 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station ML23024A1372023-02-0303 February 2023 Request for Withholding Information from Public Disclosure for LaSalle County Station, Unit Nos. 1 and 2 ML23031A1972023-01-31031 January 2023 Notification of NRC Fire Protection Team Inspection Request for Information, Inspection Report Nos. 05000373/2023011 and 05000374/2023011 IR 05000373/20220042023-01-31031 January 2023 County Station - Integrated Inspection Report 05000373/2022004 and 05000374/2022004 RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 2024-01-05
[Table view] Category:Safety Evaluation
MONTHYEARML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23286A2602023-11-0808 November 2023 Issuance of Amendment Nos. 260 and 245 to Renewed Facility Operating Licenses Relocation of Pressure and Temperature Limit Curves to the Pressure Temperature Report ML23262B4442023-09-26026 September 2023 Authorization and Safety Evaluation for Alternative Request No. I4R-14 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23073A2182023-03-22022 March 2023 Issuance of Amendment No. 258 to Renewed Facility Operating Licenses Exigent Amendment to Revise Design Basis Related to Seismic Requirements ML22341A2222022-12-28028 December 2022 Issuance of Amendment Nos. 257 and 243 to Renewed Facility Operating Licenses New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies and Changes to Core Operating Limits Report ML22293B8052022-11-30030 November 2022 Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22194A9152022-07-15015 July 2022 Proposed Alternative I4-R13 for Repair of Recirculation Flow Control Valves ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position ML22094A0012022-04-15015 April 2022 Constellation Energy Generation, LLC - Proposed Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles (Epids L-2021-LLR-0057 and L-2021-LLR-0058) ML21362A7212022-02-0404 February 2022 Issuance of Amendment Nos. 255 and 241 Revision to Technical Specifications to Incorporate Licensing Topical Report NEDE-33885P-A, Revision 1, GNF CRDA Application Methodology ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements ML21307A3422021-12-0707 December 2021 Issuance of Amendments to Adopt Reactor Pressure Vessel Water Inventory Control Enhancements (EPIDs L-2020-LLA-0253 and L-2020-LLA-0254) ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21280A0782021-10-27027 October 2021 Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148) ML21162A0692021-09-0707 September 2021 Issuance of Amendment Nos. Xxx and Yyy Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 ML21230A2062021-09-0303 September 2021 Proposed Alternative to Use ASME OM Code Case OMN-28 ML21216A2202021-08-0505 August 2021 Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting ML21188A0192021-07-28028 July 2021 Proposed Alternative I4R-12, Revision 2 from Code Surface Examinations Requirements of the ASME Code for Valves 2B33 F60A and 2B33 F60B Repairs ML21158A2282021-07-13013 July 2021 Issuance of Amendments to Renewed Facility Operating Licenses a License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink ML21166A1682021-06-25025 June 2021 ML21082A4222021-05-27027 May 2021 Issuance of Amendment Nos. 249 and 235 to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML21028A6732021-02-0303 February 2021 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011 ML20287A1302020-11-0505 November 2020 Review of Quality Assurance Program Changes ML20269A2002020-09-30030 September 2020 Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117 ML20153A8042020-07-31031 July 2020 Co. - Issuance of Amendments Revising Emergency Action RA3 ML20141L6362020-07-10010 July 2020 Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2 ML20134H9402020-07-0808 July 2020 Issuance of Amendments Revising the High Radiation Area Administrative Controls ML20113F0412020-04-30030 April 2020 Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19) ML20021A0702020-04-0606 April 2020 Issuance of Amendments to Delete License Conditions for Decommissioning Trusts ML19331A7252020-02-14014 February 2020 Issuance of Amendments Revising Emergency Action Levels ML20028E3992020-02-0404 February 2020 Proposed Alternative to Use ASME Code Case N-879 ML19269C5342019-09-27027 September 2019 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19217A3062019-09-10010 September 2019 Relief Request RV-03, Relief from the Requirements of the ASME Code Related to Pressure Isolation Valve Testing Frequency ML19218A3652019-08-29029 August 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 ML19176A0332019-08-28028 August 2019 Issuance of Amendments to Adopt TSTF-564, Safety Limit MCPR ML19192A2442019-07-18018 July 2019 Proposed Alternative to Use ASME Code Cases N-878 and N-880 ML19121A5052019-06-24024 June 2019 Issuance of Amendments to Renewed Facility Operating Licenses Removal of Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High Pressure Core Spray Diesel Generator ML19121A3172019-05-20020 May 2019 Relief Request 13R-15, Relief from the Requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&Pv) Code, Section X1, Rules for Inservice Inspection (EPID-L-2018-LLR-0123) ML19098A0342019-04-30030 April 2019 Units 1 and 2; Limerick, Units 1 and 2; Peach Bottom, Units 2 and 3, and Quad Cities, Units 1 and 2 - Revision to Approved Alternative to Use BWR Vessel and Internal Proj Guidelins ML19036A5862019-03-21021 March 2019 Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements ML19025A2882019-02-14014 February 2019 Issuance of Amendments to Renewed Facility Operating Licenses Revision of Technical Specifications to Adopt TSTF-334-A ML18304A3652019-01-16016 January 2019 2. Issuance of Amendments to Revise the Average Power Range Monitor Requirements ML18311A2652019-01-0202 January 2019 Issuance of Amendments Nos. 233 and 219 to Renewed Facility Operating Licenses License Amendment Request for Temporary Extensions to Technical Specifications ML18278A0302018-12-19019 December 2018 Issuance of Amendments 232, 218 to Renewed Facility Operating Licenses Request to Revise the Technical Specifications Surveillance Requirement to Revise the Lower Setpoint Tolerance for Safety/Relief Valves ML18254A3672018-10-29029 October 2018 County 1 & 2; and Quad Cities 1 & 2 - Issuance of Amendments 220, 259, 252, 231, 217, 271 and 266 to Revise Technical Specification Requirements for Inoperable Snubbers ML18226A2022018-10-15015 October 2018 Issuance of Amendments to Renewed Facility Operating Licenses Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control 2023-09-26
[Table view] |
Text
May 7, 2008 Mr. Charles G. Pardee Chief Nuclear Officer and Senior Vice President Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LASALLE COUNTY STATION, UNITS 1 AND 2 - REQUEST FOR RELIEF FROM ASME OM CODE FOR THE THIRD 10-YEAR PUMP AND VALVE INSERVICE TESTING PROGRAM INTERVAL - RP-02 (TAC NOS. MD6867 AND MD6868)
Dear Mr. Pardee:
By letter to the Nuclear Regulatory Commission (NRC), dated September 28, 2007, Exelon Generation Company LLC (the licensee), submitted Relief Request (RR) RP-02 for the third 10-year inservice testing (IST) program interval at LaSalle County Station (LSCS), Units 1 and 2.
The licensee requested relief from certain IST requirements of the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants. This RR was previously submitted by letter dated September 29, 2006, and was withdrawn by letter dated September 4, 2007.
The NRC staff has completed its review of the RR and is providing the attached safety evaluation. Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55(a)(3)(ii), RR RP-02 is authorized on the basis that complying with the specified requirements would result in hardship without a compensating increase in the level of quality and safety. The proposed alternative provides reasonable assurance that the subject pumps are operationally ready.
The LSCS third 10-year IST intervals started on October 12, 2007. The RR is authorized for the third 10-year IST interval, which will end October 11, 2017.
Sincerely,
/RA/
Russell Gibbs, Chief Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374
Enclosure:
Safety Evaluation cc w/encls: See next page
May 7, 2008 Mr. Charles G. Pardee Chief Nuclear Officer and Senior Vice President Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LASALLE COUNTY STATION, UNITS 1 AND 2 - REQUEST FOR RELIEF FROM ASME OM CODE FOR THE THIRD 10-YEAR PUMP AND VALVE INSERVICE TESTING PROGRAM INTERVAL - RP-02 (TAC NOS. MD6867 AND MD6868)
Dear Mr. Pardee:
By letter to the Nuclear Regulatory Commission (NRC), dated September 28, 2007, Exelon Generation Company LLC (the licensee), submitted Relief Request (RR) RP-02 for the third 10-year inservice testing (IST) program interval at LaSalle County Station (LSCS), Units 1 and 2.
The licensee requested relief from certain IST requirements of the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants. This RR was previously submitted by letter dated September 29, 2006, and was withdrawn by letter dated September 4, 2007.
The NRC staff has completed its review of the RR and is providing the attached safety evaluation. Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55(a)(3)(ii), RR RP-02 is authorized on the basis that complying with the specified requirements would result in hardship without a compensating increase in the level of quality and safety. The proposed alternative provides reasonable assurance that the subject pumps are operationally ready.
The LSCS third 10-year IST intervals started on October 12, 2007. The RR is authorized for the third 10-year IST interval which will end October 11, 2017.
Sincerely,
/RA/
Russell Gibbs, Chief Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374
Enclosure:
Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 RidsNrrOd RidsAcrsAcnw&mMailCenter RidsOgcRp RidsNrrLAEWhitt RidsNrrPMSSands RidsRgn3MailCenter RidsNrrDciCptb RWolfgang, NRR Adams Accession No.: ML080930122 *SE dated NRR-106 OFFICE LPL3-2/PM LPL3-2/LA DCI/CPTB/BC* OGC LPL3-2/BC NAME SSands EWhitt JMcHale PMoulding RGibbs DATE 04 /24/08 04 /24/08 02 / 14 /08 04 / 10 /08 05/7/08 OFFICIAL RECORD COPY
LaSalle County Station, Units 1 and 2 cc:
Corporate Distribution Exelon Generation Company, LLC Via e-mail LaSalle Distribution Exelon Generation Company, LLC Via e-mail LaSalle Resident Inspector U.S. Nuclear Regulatory Commission Via e-mail Phillip P. Steptoe, Esquire Sidley and Austin Via e-mail Assistant Attorney General Chicago, IL 60603 Via e-mail Chairman LaSalle County Board Via e-mail Attorney General Via e-mail Chairman Illinois Commerce Commission Via e-mail Illinois Emergency Management Agency Division of Disaster Assistance &
Preparedness Via e-mail Robert Cushing, Chief, Public Utilities Division Illinois Attorney General's Office 100 W. Randolph Street Chicago, IL 60601
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE THIRD 10-YEAR PUMP AND VALVE INSERVICE TESTING INTERVAL - RP-02 EXELON GENERATION COMPANY, LLC LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374
1.0 INTRODUCTION
By letter to the Nuclear Regulatory Commission (NRC) dated September 28, 2007, Agencywide Documents Access Management Systems (ADAMS) Accession No. ML072710656, Exelon Generation Company, LLC (the licensee), submitted a Relief Request (RR) RP-02 for the third 10-year inservice testing (IST) program interval at the LaSalle County Station (LSCS), Units 1 and
- 2. The licensee requested relief from certain IST requirements of the 2001 Edition through 2003 Addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code). The licensee previously submitted this RR by letter dated September 29, 2006 (ADAMS No. ML062970430), and withdrew this RR by letter dated September 4, 2007 (ADAMS No. ML072480229). The NRC staff evaluation of the RR is contained herein. The LSCS third 10-year IST intervals commenced on October 12, 2007.
The ASME Code that was in affect during the Second 10-Year IST interval [ASME Boiler and Pressure Vessel Code,Section XI (1989 Edition with no Addenda)] did not require "Comprehensive Pump Testing." As such, LaSalle Station did not have a requirement for comprehensive pump testing, and therefore, there is no previous test date or a previous relief requested for RP-02 during the Second 10-Year IST Interval.
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a, requires that IST of certain ASME Code Class 1, 2, and 3 pumps and valves be performed at 120-month (10-year)
IST program intervals in accordance with the specified ASME OM Code and applicable addenda incorporated by reference in the regulations, except where alternatives have been authorized, or relief has been requested by the licensee and granted by the NRC, pursuant to paragraphs (a)(3)(i), (a)(3)(ii), or (f)(6)(i) of 10 CFR 50.55a. In accordance with 10 CFR 50.55a(f)(4)(ii), licensees are required to comply with the requirements of the latest edition and addenda of the ASME OM Code incorporated by reference in the regulations 12 months prior to the start of each 120-month IST program interval. In accordance with 10 CFR 50.55a(f)(4)(iv), IST of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a(b),
subject to NRC approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions and addenda are met.
Pursuant to 10 CFR 50.55a(a)(3), the NRC may authorize alternatives to the relevant ASME OM Code requirements if the licensee demonstrates that: (1) the proposed alternatives provide an acceptable level of quality and safety; or (2) compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. NRC guidance contained in Generic Letter (GL) 89-04, Guidance on Developing Acceptable Inservice Testing Programs, describes certain acceptable alternatives to ASME Code requirements. Further guidance is given in GL 89-04, Supplement 1, and NUREG-1482 Revision 1, Guidance for Inservice Testing at Nuclear Power Plants. The NRCs findings with respect to granting or denying the IST program relief requests are given below:
3.0 TECHNICAL EVALUATION
3.1 Pump Relief Request RP-02 3.1.1 Code Requirements The licensee requested relief from ISTB-5123, Comprehensive Test Procedure.
ISTB-5123 requires that comprehensive tests be conducted with the pump operating at a specified reference point, and that the test parameters shown in Table ISTB-3000-1 be determined and recorded. Table ISTB-3000-1 includes the measurement of flow.
Relief was requested for the following pumps:
Pump Description Class Category Unit 1E22-C003 High Pressure Core Spray 2 Group A 1 (HPCS) Water Leg Pump 1E21-C002 Low Pressure Core Spray 2 Group A 1 (LPCS) Water Leg Pump 1E12-C003 Residual Heat Removal 2 Group A 1 (RHR) Water Leg Pump 1E51-C003 Reactor Core Isolation 2 Group A 1 Cooling (RCIC) Water Leg Pump 2E22-C003 HPCS Water Leg Pump 2 Group A 2 2E21-C002 LPCS Water Leg Pump 2 Group A 2 2E12-C003 RHR Water Leg Pump 2 Group A 2 2E51-C003 RCIC Water Leg Pump 2 Group A 2 3.1.2 Licensees Basis for Requesting Relief The licensee states:
ISTB-5123 requires performance of comprehensive pump testing of the parameters listed in Table ISTB-3000-1. Table ISTB-3000-1 includes the measurement of flow, and there are no existing flow instruments associated with these pumps. Installation of flow
instruments would be a hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The primary purpose of these pumps is to maintain the HPCS, LPCS, RCIC, and RHR pump discharge lines filled to limit the potential for water hammer upon associated pump initiation. Once the supported pump (e.g., HPCS, RHR, etc.) is in operation, the associated water leg pump serves no further safety related function. The amount of flow delivered by each water leg pump is dependent upon each supported systems leakage rate. Each water leg pump is capable of delivering approximately 50 gallons per minute (gpm). None of the listed water leg pumps have instrumentation installed in their discharge lines for measuring flow rates.
While flow measurement instrumentation is provided downstream of the water leg pumps branch connection to its associated support system, during power operation the water leg pump is unable to generate sufficient pressure to flow through the associated flow element into the reactor vessel. Even if the water leg pump was capable of developing a head sufficient to inject into the reactor vessel during power operation, the flow measurement instrumentation, which is designed to measure flow developed by either a HPCS (0-8,000 gpm), LPCS (0-10,000 gpm), RHR (0-10,000 gpm), or RCIC (0-700 gpm) pump, is not capable of measuring such small flows developed by a water leg pump (i.e., approximately 50 gpm).
The application of temporary flow instrumentation (ultrasonic) cannot be utilized, as there does not exist a run of piping long enough that would allow for an accurate measurement.
The quarterly group A testing as modified by LaSalle pump relief request RP-01 will continue to be performed during the stipulated conditions that the RCS pressure is greater than the discharge of the associated water leg pump, and that the supported system pump is not in operation during the testing of the associated water leg pump.
Comprehensive pump testing prescribes that pump parameters are measured while the pump is operating at a flow rate within 20% of the pumps design flow. These water leg pumps do not have a safety-related design flow rate. These pumps operate in a keep ready mode, maintaining the supported systems piping pressurized with water, which is dependent upon each individual systems leakage rate.
The remaining differences between comprehensive pump testing and group A testing is the accuracy of the instruments used in measuring the differential pressure (Table ISTB-3500-1) as well as the acceptance criteria associated with the pumps differential pressure (Table ISTB-5100-1).
These water leg pumps are tested quarterly by isolating them from their support system piping and measuring their pressure and vibration parameters as they flow through their minimum flow line, through a minimum flow orifice. As there is no flow measurement taken as a result of the system configuration, variation of the system resistance is not used.
The utilization of more accurate test instrumentation and acceptance criteria under these conditions would result in hardship without a compensating increase in the level of quality or safety.
3.1.3 Licensees Proposed Alternative Testing The licensee states:
LaSalle County Station Units 1 and 2 will continue to monitor the subject pumps for degradation by measuring and recording pump inlet pressure, discharge pressure (from which differential pressure is calculated), and vibration. The differential pressure and vibration data will be trended as directed by ISTB-5121 (Group A Test Procedure) as amended by relief request RP-01. These measurements are taken quarterly during normal plant operation, when the supported systems pump is not in operation and reactor coolant system pressure is greater than the water leg pumps discharge pressure. Measurement and trending of these parameters under these stated conditions will provide satisfactory indication of operational readiness as well as the ability to detect potential degradation. In addition, the main emergency core cooling system (ECCS) pump headers each have a low pressure sensor which continuously monitors the operability of the respective water leg pump, and alarms upon reaching their low setpoints. Technical specification surveillance requirements (SR) (i.e., SR 3.5.1.1, SR 3.5.2.3, and SR 3.5.3.1) also verify operability of the water leg pumps by verifying flow through a high point vent on a monthly basis.
Vibration measurement will continue to be obtained under normal operating conditions and evaluated in accordance with ISTB-5121(d) and ISTB-5121(e) (Group A testing).
The differential pressure across the pump will also continue to be determined quarterly through plant procedures utilizing each pumps minimum flow line in accordance with ISTB-5121(c) and ISTB-5121(e). Differential pressure and vibration will continue to be trended. In addition, LaSalle County Station Units 1 and 2 verifies operability of these pumps through continuous monitoring of the HPCS, LPCS, RHR, and RCIC pump discharge line pressures that are monitored in the control room by alarm.
Comprehensive testing is not applicable as these pumps do not provide a safety-related function beyond providing for the readiness of their supported systems pump and thus have no acceptance criteria for a comprehensive test.
3.1.4 Evaluation ISTB-5123 requires that each water leg pump be comprehensively tested by operating the pump at a specified reference point and recording the measured flow, differential pressure, and bearing vibration for comparison with the ASME OM Code acceptance criteria. The design of the HPCS, LPCS, RHR, and RCIC water leg pumps does not enable a comprehensive test to be readily performed in accordance with the ASME OM Code. The necessary flow instrumentation is not installed in the systems and a plant modification would be necessary to install the flow instrumentation, which would be a hardship to the licensee. Temporary ultrasonic flow instrumentation cannot be used because there is not a run of piping long enough to allow for an accurate measurement. The licensee proposes to monitor the pumps for
mechanical degradation with vibration monitoring, and for hydraulic degradation by measuring and recording pump inlet pressure and discharge pressure, and calculating differential pressure.
The vibration and differential pressure data will be trended as directed by ISTB-5121 (Group A Test Procedure) as amended by RR RP-01. Also, the operability of the water leg pumps will be ensured by verifying flow (but not measuring flow) through a high point vent on the ECCS pump discharge header piping on a monthly basis.
While the proposed IST would not be as complete as it would be if the ASME OM Code requirements for a comprehensive pump test were imposed, 10 CFR 50.55a does include provisions for hardships due to design limitations, as the initial imposition of the ASME OM Code requirements was subsequent to the design and construction of a number of nuclear plants, including LSCS. For the water leg pumps, which are continuously operating pumps, the safety function is to keep the ECCS pump discharge header piping in a filled condition to prevent water hammer upon the start of the main ECCS pump. The actual output and hydraulic performance of the water leg pumps are not critical to the safety function, as long as the pumps are capable of maintaining the piping full of water. Each ECCS pump discharge header piping has a low pressure sensor. An alarm would promptly alert plant operators whenever the water leg pumps do not maintain the piping pressure to a set alarm level. In addition, vibration data will be indicative of levels trending toward unacceptable values and should allow time for the licensee to take corrective actions before the pumps fail. The proposed alternative provides a reasonable assurance of operational readiness of the water leg pumps because (1) differential pressure and bearing vibration are measured and trended, (2) alarms are present which provide a continuous monitoring of degradation in the pressure of the ECCS pump discharge header piping, and (3) flow is verified monthly by opening a vent on the main header piping to observe discharge. Accordingly, after reviewing the licensees proposed alternative, the NRC staff concludes that requiring compliance with the specified ASME OM Code requirement at LSCS would not result in a compensating increase in the level of quality and safety.
4.0 CONCLUSION
The NRC staff concludes that requiring the licensee to comply with the specified ASME OM Code requirements would result in hardship without a compensating increase in the level of quality and safety. Accordingly, the licensees proposed alternative is authorized pursuant to 10 CFR 50.55a(a)(3)(ii) for the third 10-year IST intervals at LSCS.
Principal Contributor: R. Wolfgang, NRR Date: May 7, 2008