Letter Sequence Other |
---|
|
|
MONTHYEARML0801405882008-01-22022 January 2008 RAI Letter Request for Relief 13R-01 Associated with the Third 10-Year Inservice Inspection Interval, Inspection Program Plan Risk-Informed Inservice Inspection of Piping Project stage: RAI RS-08-008, Response to RAI Related to Relief Request I3R-01, Alternate Risk-Informed Selection and Examination Criteria for Examination Category B-F, B-J, C-F-1, and C-F-2 Pressure Retaining Piping Welds.2008-02-0101 February 2008 Response to RAI Related to Relief Request I3R-01, Alternate Risk-Informed Selection and Examination Criteria for Examination Category B-F, B-J, C-F-1, and C-F-2 Pressure Retaining Piping Welds. Project stage: Response to RAI ML0809402152008-04-29029 April 2008 RR 13R-01, Associated with the Third 10-Year Interval Project stage: Other 2008-02-01
[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
April 29, 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 - RELIEF REQUEST I3R-01, ASSOCIATED WITH THE THIRD 10-YEAR INTERVAL FOR LASALLE COUNTY STATION, UNITS 1 AND 2 (TAC NOS. MD5457 AND MD5458)
Dear Mr. Pardee:
By letter to the Nuclear Regulatory Commission (NRC), dated April 30, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML071280395), as supplemented by letter dated February 1, 2008 (ADAMS Accession No. ML080320580), Exelon Generation Company LLC (the licensee), submitted a Relief Request (RR) for the third 10-year interval inservice inspection (ISI) plan for LaSalle County Station (LSCS), Units 1 and 2. The licensee requested relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI requirements for the selection and examination of Class 1 and 2 piping welds. The RR I3R-01, submitted by the licensee, proposes as an alternative to the ASME Code, to use the methodology contained in Electric Power Research Institute Topical Report 112657, Revision B-A. The NRC staff has approved this methodology in a safety evaluation dated October 28, 1999.
On September 12, 2007, NRC granted relief requests to LSCS for its third 10-year interval ISI plan, dated April 30, 2007, for RR Nos. I3R-03, I3R-04, I3R-08, I3R-00, and I3R-10 (ADAMS Accession No. ML072550452).
The licensee had requested, and received, relief for LSCS for the second 10-year ISI interval.
The licensee is requesting the same risk-informed (RI) ISI RR for the third 10-year interval. The NRC staff has evaluated the licensees RI-ISI RR for the third 10-year interval and finds that the licensee has addressed the necessary issues to demonstrate compliance with regulatory-related requirements and has provided sufficient assurance that the proposed RI-ISI program provides an acceptable level of quality and safety.
The RR is authorized for the third 10-year interval which ends on September 30, 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/encl: See next page
ML080320580), Exelon Generation Company LLC (the licensee), submitted a Relief Request (RR) for the third 10-year interval inservice inspection (ISI) plan for LaSalle County Station (LSCS), Units 1 and 2. The licensee requested relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI requirements for the selection and examination of Class 1 and 2 piping welds. The RR I3R-01, submitted by the licensee, proposes as an alternative to the ASME Code, to use the methodology contained in Electric Power Research Institute Topical Report 112657, Revision B-A. The NRC staff has approved this methodology in a safety evaluation dated October 28, 1999.
On September 12, 2007, NRC granted relief requests to LSCS for its third 10-year interval ISI plan, dated April 30, 2007, for RR Nos. I3R-03, I3R-04, I3R-08, I3R-00, and I3R-10 (ADAMS Accession No. ML072550452).
The licensee had requested, and received, relief for LSCS for the second 10-year ISI interval.
The licensee is requesting the same risk-informed (RI) ISI RR for the third 10-year interval. The NRC staff has evaluated the licensees RI-ISI RR for the third 10-year interval and finds that the licensee has addressed the necessary issues to demonstrate compliance with regulatory-related requirements and has provided sufficient assurance that the proposed RI-ISI program provides an acceptable level of quality and safety.
The RR is authorized for the third 10-year interval which ends on September 30, 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/encl: See next page DISTRIBUTION:
PUBLIC LPL3-2 R/F RidsNrrAdes RidsNrrOd RidsAcrsAcnw&mMailCenter RidsOgcRp RidsNrrLAEWhitt RidsNrrDorlLpl3-2 RidsNrrPMSSands RidsRgn3MailCenter RidsNrrDraApla JAdams, EDO Region III Adams Accession No.: ML080940215 *SE Dated NRR-106 *w/corrections OFFICE LPL3-2/PM LPL3-2/LA DRA/APLA/BC OGC* LPL3-2/BC NAME SSands EWhitt MRubin* JBiggins RGibbs DATE 04 /29/08 04 /29/08 03 / 04 /08 04 / 16 /08 04 /29/08 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 RELIEF REQUEST NO. I3R-01, ASSOCIATED WITH THE THIRD 10-YEAR INSERVICE INSPECTION INTERVAL 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, the Commission) dated April 30, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML071280395), as supplemented by letter dated February 1, 2008 (ADAMS Accession No. ML080320580), Exelon Generation Company, LLC (the licensee), requested approval of alternate risk-informed inservice inspection (RI-ISI) selection and examination criteria at the LaSalle County Station (LSCS), Units 1 and 2. The licensees RI-ISI program is an alternative pursuant to Section 50.55a(a)(3)(i) of Title 10 of the Code of Federal Regulations (10 CFR).
The scope of the alternate RI-ISI program, I3R-01, is applicable to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, 2001 Edition through the 2003 Addenda, Class 1 and 2 piping, Categories B-F, B-J, C-F-1, and C-F-2 piping welds.
The NRC staff had approved a RI-ISI program for use during the second 10-year interval which started on November 23, 1994 and ended on October 28, 2007 for LSCS, Unit 1; and from October 17, 1994, to July 4, 2007, for LSCS, Unit 2 (ADAMS Accession No. ML013610078).
The licensee is proposing to extend the RI-ISI to the new, third 10-year interval which starts on October 1, 2007, and ends on September 30, 2017, for both Units 1 and 2.
By letter dated September 22, 2006 (ADAMS Accession No. ML062720153), the licensee informed the NRC of their intention to synchronize the ten-year ISI intervals between LSCS Units 1 and 2 for ASME Code classes 1, 2, and 3. The implementation would be based on the provisions of ASME Section XI paragraph IWA-2430 Inspection Intervals. In accordance with Program B, each inspection interval may be reduced or extended up to one year. Since the provisions of ASME Section XI paragraph IWA-2430(d) were met, a relief request to extend the interval in accordance with 10 CFR 50.55a, Codes and Standards, paragraph (a)(3)(i) was not required.
2.0 REGULATORY EVALUATION
Section 50.55a(g) of 10 CFR requires that ISI of the ASME Code Class 1, 2, and 3 components be performed in accordance with Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components and applicable addenda, except where specific relief has been granted by
the Commission pursuant to 10 CFR 50.55a(g)(6)(i). The regulation 10 CFR 50.55a(a)(3) states in part, that alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if the licensee demonstrates that the proposed alternatives would provide an acceptable level of quality and safety, or if the specified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The proposed program is developed consistent with the staff approved RI-ISI process and methodology delineated in Electric Power Research Institute (EPRI) (TR)-112657, Revision B-A, Revised Risk-Informed Inservice Inspection Evaluation Procedure as approved by the NRC staff for use during the second interval. The ISI program retains the fundamental requirements of the ASME Code, such as inspection methods, acceptance guidelines, pressure testing, corrective measures, documentation requirements and quality control requirements.
The NRC staff reviewed the proposed RI-ISI program based on guidance and acceptance criteria provided in the following documents:
- EPRI TR-112657, Revision B-A, Revised Risk-Informed Inservice Inspection Evaluation Procedure, Final Report, December 1999.
- NRC Regulatory Guide 1.178, Revision 1, An Approach for, Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspection of Piping, U.S. NRC, September 2003.
- NUREG-0800, Chapter 3.9.8, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, Risk-Informed Inservice Inspection of Piping, U.S.
NRC, September 2003.
3.0 TECHNICAL EVALUATION
The licensee is requesting relief that would permit continued use of a previously approved RI-ISI program plan in the third 10-year ISI interval instead of the ASME Code,Section XI program.
An acceptable RI-ISI program plan is expected to meet the five key principles of risk-informed decisionmaking, discussed in Regulatory Guide (RG) 1.174 and RG 1.178. These principles are:
- 1) The proposed change meets the current regulations unless it is explicitly related to a requested exemption or rule change.
- 2) The proposed change is consistent with the defense-in-depth philosophy.
- 3) The proposed change maintains sufficient safety margins.
- 4) When proposed changes result in an increase in core damage frequency and/or large early release frequency (LERF), the increases should be small and consistent with the intent of the Commissions Safety Goal Policy Statement.
- 5) The impact of the proposed change should be monitored by using performance measurement strategies.
The first principle is met in this RR because an alternative ISI program may be authorized pursuant to 10 CFR 50.55a(3)(i) and therefore, an exemption request is not required.
The second and third principles require assurance that the alternative program is consistent with the defense-in-depth philosophy and that sufficient safety margins are maintained, respectively.
The methodology used to develop the third 10-year RI-ISI program interval is unchanged from the methodology approved for use in the second 10-year RI-ISI program interval. Assurance that the second and third principles are met is based on the application of the approved methodology and not on the particular inspection locations selected. Therefore, the second and third principles are met.
The fourth principle requires an estimate of the change in risk, and the change in risk is dependent on the number and location of inspections in the proposed ISI program compared to the number and location of inspections that would be inspected using the requirements of ASME Code,Section XI. The topical report EPRI TR-112657 requires that a change in risk measurement must consider the discontinuance of ASME Code required inspections, as well as any new inspections resulting from the application of its methodology. The licensee states in Reference 2, that a complete risk evaluation following the EPRI methodology was performed in 2007. The update was completed as part of the living program process using the current PRA model and the latest element selections. The licensee reports the changes in CDF and LERF for LSCS, Unit 1 to be 6.89E-9/yr and 4.76E-9/yr. For LSCS, Unit 2, the estimate change in CDF and LERF are 8.40E-9/yr and 6.39E-9/yr. The licensee also reported the system level changes for all the systems included in the scope of the submittal. All of the estimated changes in risk are below the EPRI guideline for acceptable estimated changes in CDF and LERF.
The fifth principle of RI decisionmaking requires that the impact of the proposed change should be monitored by using performance measurement strategies. In addition to the complete risk evaluation described above, the licensee states that the evaluation and ranking procedure including the consequence evaluation and degradation mechanism assessment are continually applied to maintain the risk categorization and element selection methods of EPRI TR-112657.
These portions of the program are also reevaluated as major revisions of the site PRA that occur and modifications to the plant configuration were made on April 30. 2007. Thus, the program continues to be a living program and therefore satisfies the fifth principle.
Based on the above discussion, the NRC staff concludes that the five key principles of RI decision making are satisfied by the licensees proposed third 10-year RI-ISI program, and, therefore, the proposed program for the third 10-year ISI interval is acceptable.
4.0 CONCLUSION
Based on the information provided in the licensees submittals, the NRC staff has determined that the proposed alternative provides an acceptable level of quality and safety, and therefore the proposed alternative is authorized pursuant to 10 CFR 50.55a(a)(3)(i) for the third 10-year ISI inspection interval at LSCS.
Principal Contributor: D. Chung, NRR Date: April 29, 2008