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| | issue date = 07/18/2016 | | | issue date = 07/18/2016 |
| | title = Report on the Safety Aspects of the License Renewal Application of the LaSalle County Station, Units 1 and 2 | | | title = Report on the Safety Aspects of the License Renewal Application of the LaSalle County Station, Units 1 and 2 |
| | author name = Bley D C | | | author name = Bley D |
| | author affiliation = NRC/ACRS | | | author affiliation = NRC/ACRS |
| | addressee name = Burns S G | | | addressee name = Burns S |
| | addressee affiliation = NRC/Chairman | | | addressee affiliation = NRC/Chairman |
| | docket = 05000373, 05000374 | | | docket = 05000373, 05000374 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 July 18, 2016 The Honorable Stephen G. Burns Chairman U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 |
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| July 18, 2016 | |
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| The Honorable Stephen G. Burns Chairman U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REPORT ON THE SAFETY ASPECTS OF THE LICENSE RENEWAL APPLICATION OF THE LASALLE COUNTY STATION, UNITS 1 AND 2 | | REPORT ON THE SAFETY ASPECTS OF THE LICENSE RENEWAL APPLICATION OF THE LASALLE COUNTY STATION, UNITS 1 AND 2 |
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| ==Dear Chairman Burns:== | | ==Dear Chairman Burns:== |
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| During the 635 th meeting of the Advisory Committee on Reactor Safeguards (ACRS), July 6 - 8, 2016, we completed our review of the license renewal application for the LaSalle County Station, Units 1 and 2 (LaSalle) and the final safety evaluation report (SER) prepared by the NRC staff. Our Subcommittee on Plant License Renewal reviewed this matter during a meeting on April 19, 2016. During these reviews, we had the benefit of discussions with representatives of the NRC staff and the Exelon Generation Company, LLC (Exelon or the applicant). We also had the benefit of the referenced documents. This report fulfills the requirement of 10 CFR 54.25 that the ACRS review and report on all license renewal applications. | | During the 635th meeting of the Advisory Committee on Reactor Safeguards (ACRS), July 6 - 8, 2016, we completed our review of the license renewal application for the LaSalle County Station, Units 1 and 2 (LaSalle) and the final safety evaluation report (SER) prepared by the NRC staff. Our Subcommittee on Plant License Renewal reviewed this matter during a meeting on April 19, 2016. During these reviews, we had the benefit of discussions with representatives of the NRC staff and the Exelon Generation Company, LLC (Exelon or the applicant). We also had the benefit of the referenced documents. This report fulfills the requirement of 10 CFR 54.25 that the ACRS review and report on all license renewal applications. |
| | CONCLUSION AND RECOMMENDATION |
| | : 1. The programs established and committed to by Exelon to manage age-related degradation provide reasonable assurance that LaSalle can be operated in accordance with its current licensing bases for the period of extended operation without undue risk to the health and safety of the public. |
| | : 2. Exelons application for renewal of the operating licenses for LaSalle should be approved. |
| | BACKGROUND LaSalle is located approximately 55 miles southwest of Chicago, Illinois. Units 1 and 2 are of a boiling water reactor (BWR) Type 5 (BWR/5) design. Each primary containment is a Mark II type, safety-related seismic Category I structure consisting of a steel dome head and post-tensioned concrete wall standing on a base mat of conventionally reinforced concrete. General Electric provided the nuclear steam supply system, and Sargent & Lundy designed and constructed the balance of the plant. Each unit has a licensed power output of 3,546 megawatts thermal, with a gross electrical output of approximately 1,207 megawatts. The NRC issued the construction permits (CPRR-99 and CPRR-100, respectively) for Units 1 and 2 on September 7, 1973. The NRC issued the operating licenses for Unit 1 and Unit 2 on April 17, 1982, and December 16, 1983, respectively. |
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| CONCLUSION AND RECOMMENDATION
| | 2 In this application, Exelon requests renewal of the operating licenses (Facility Operating License Nos. NPF-11 and NPF-18) for a period of 20 years beyond the current expiration date of April 17, 2022, for Unit 1, and December 16, 2023, for Unit 2. |
| : 1. The programs established and committed to by Exelon to manage age-related degradation provide reasonable assurance that LaSalle can be operated in accordance with its current licensing bases for the period of extended operation without undue risk to the health and safety of the public.
| | DISCUSSION In its final SER, dated June 2016, the staff documented its review of the license renewal application and other information submitted by the applicant and obtained through staff audits and inspections at the plant sites. The staff reviewed the completeness of the identification of structures, systems, and components (SSCs) that are within the scope of license renewal; the integrated plant assessment process; the identification of plausible aging mechanisms associated with passive, long-lived components; the adequacy of the Aging Management Programs (AMPs); and identification and assessment of Time-Limited Aging Analyses (TLAAs) requiring review. |
| : 2. Exelon's application for renewal of the operating licenses for LaSalle should be approved.
| | Exelons LaSalle license renewal application identified the SSCs that fall within the scope of license renewal. The application is largely consistent with the Generic Aging Lessons Learned (GALL) Report (NUREG-1801). Deviations and exceptions are documented and justified. |
| | Exelon will implement 46 AMPs for license renewal, comprised of 35 existing programs and 11 new programs. Nineteen of the 46 AMPs are consistent with the GALL Report without enhancements or exceptions. Nineteen AMPs are consistent with enhancements. Three AMPs are consistent with exceptions. Three AMPs are consistent with enhancements and exceptions. |
| | Two AMPs, Service Level III and Service Level III Augmented Coatings Monitoring and Maintenance Program, and Unit 2 Inspection of The American Society of Mechanical Engineers (ASME) Code Class 1 Small-Bore Piping Program, are plant-specific. |
| | The license renewal application includes six programs with exceptions to the GALL Report. We reviewed these programs (Flow-Accelerated Corrosion, Reactor Vessel Surveillance, Compressed Air Monitoring, Fire Water System, Reactor Head Closure Stud Bolting, and Water Chemistry). We conclude that the six GALL programs with exceptions are acceptable. |
| | The staff conducted license renewal audits and performed license renewal inspections at LaSalle. The audits verified the adequacy of the scoping and screening methodology for AMPs, the appropriateness of the aging management review, and the acceptability of the TLAAs. The inspection verified that the license renewal requirements are implemented appropriately. Both the inspection, and the report of that inspection, are thorough. Based on the audits, the inspection, and the staff reviews related to this license renewal application, the staff concluded in the final SER that the proposed activities will manage the effects of aging of SSCs identified in the application and that the intended functions of these SSCs will be maintained during the period of extended operation. The staff concluded that Exelon has demonstrated that the effects of aging at LaSalle will be adequately managed so that the intended function(s) will be maintained consistent with the current licensing basis for the period of extended operation, as required by 10 CFR 54.21(a)(3). |
| | Two open items were resolved between our subcommittee meeting on April 19, 2016, and our final review on July 6, 2016. The open items pertained to 1) enhanced visual testing examination coverage and 2) limited volumetric examination coverage. Resolution of the open items is as follows. |
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| BACKGROUND
| | 3 EVT-1 Examination Coverage - BWR Vessel ID Attachment Welds Aging Management Program This item addresses changes to the BWR Vessel Internals Program (BWRVIP) guidance for EVT-1 viewing angle limitation that reduced effective examination coverage. Coverage requirements were not specified. The staffs concern was the programs ability to credit EVT-1s with 0% coverage; therefore, the staff raised the question of program adequacy. Exelon provided information to the NRC on February 25, 2016, in response to Request for Additional Information B.2.1.4-1 that 1) revised the procedure to eliminate the possibility that EVT-1 weld exam coverage of 0% could be acceptable and 2) communicated that visual inspections are performed of entire accessible Vessel ID attachment welds by a certified nondestructive examination examiner. EVT-1 examination coverage is maximized, consistent with BWRVIP A and BWRVIP-03 guidance. |
| | Limited Volumetric Exam Coverage - BWR Stress Corrosion Cracking Aging Management Program This item addresses examination coverage for augmented weld inspections. The staff was concerned that program effectiveness could not be assured without documented bases for crediting limited weld inspections. Exelon provided information to the NRC on February 25, 2016, stating that 90% examination coverage is considered the minimum acceptable examination coverage, without evaluation, during the period of extended operation. If examination coverage is less than 90%, procedures require action to maximize the extent of examination coverage. In addition, if the examinations with less than 90% coverage are required to meet ASME Code Section XI requirements, a relief request is required. Exelon changed procedures for examinations that are required to meet the AMP, but not to meet ASME code requirements. The new procedures require an engineering technical evaluation equivalent to a relief request. |
| | We agree with the staff that there are no issues related to the matters described in 10 CFR 54.29(a) (1) and (a) (2) that preclude renewal of the operating licenses for LaSalle. The programs established and committed to by Exelon provide reasonable assurance that LaSalle can be operated in accordance with its current licensing basis for the period of extended operation without undue risk to the health and safety of the public. The Exelon application for renewal of the operating licenses for LaSalle, Units 1 and 2 should be approved. |
| | Sincerely, |
| | /RA/ |
| | Dennis C. Bley Chairman |
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| LaSalle is located approximately 55 miles southwest of Chicago, Illinois. Units 1 and 2 are of a boiling water reactor (BWR) Type 5 (BWR/5) design. Each primary containment is a Mark II type, safety-related seismic Category I structure consisting of a steel dome head and post-tensioned concrete wall standing on a base mat of conventionally reinforced concrete. General Electric provided the nuclear steam supply system, and Sargent & Lundy designed and constructed the balance of the plant. Each unit has a licensed power output of 3,546
| | 3 REFERENCES |
| | | : 1. Exelon Generation Company, LLC, LaSalle County Station, Units 1 and 2, Application for Renewed Operating Licenses, December 9, 2014 (ML14343A840). |
| megawatts thermal, with a gross electrical output of approximately 1,207 megawatts. The NRC issued the construction permits (CPRR-99 and CPRR-100, respectively) for Units 1 and 2 on September 7, 1973. The NRC issued the operating licenses for Unit 1 and Unit 2 on April 17, 1982, and December 16, 1983, respectively.
| | : 2. U.S. Nuclear Regulatory Commission, Safety Evaluation Report Related to the License Renewal of LaSalle County Station, Units 1 and 2, June 2016 (ML16126A503). |
| 2 In this application, Exelon requests renewal of the operating licenses (Facility Operating License Nos. NPF-11 and NPF-18) for a period of 20 years beyond the current expiration date of April 17, 2022, for Unit 1, and December 16, 2023, for Unit 2. | | : 3. U.S. Nuclear Regulatory Commission, Safety Evaluation Report with Open items Related to the License Renewal of LaSalle County Station, Units 1 and 2, February 2016 (ML16053A439). |
| DISCUSSION
| | : 4. U.S. Nuclear Regulatory Commission, NUREG 1801, Generic Aging Lessons Learned (GALL) Report, Revision 2, December 2010 (ML103490041). |
| | | : 5. U.S. Nuclear Regulatory Commission, Aging Management Programs Audit Report Regarding LaSalle County Station, Units 1 and 2 (TAC NOS. MF5347 and MF5346), |
| In its final SER, dated June 2016, the staff documented its review of the license renewal application and other information submitted by the applicant and obtained through staff audits and inspections at the plant sites. The staff reviewed the completeness of the identification of structures, systems, and components (SSCs) that are within the scope of license renewal; the integrated plant assessment process; the identification of plausible aging mechanisms associated with passive, long-lived components; the adequacy of the Aging Management Programs (AMPs); and identification and assessment of Time-Limited Aging Analyses (TLAAs)
| | September 22, 2015 (ML15196A115). |
| | | : 6. U.S. Nuclear Regulatory Commission, Scoping and Screening Methodology Audit Report Regarding LaSalle County Station, Units 1 and 2 (TAC NOS. MF5347 and MF5346), May 8, 2015 (ML15104A782). |
| requiring review.
| | : 7. U.S. Nuclear Regulatory Commission, LaSalle County Station, Units 1 and 2 License Renewal Scoping, Screening, and Aging Management Inspection Report 05000373/2015008; 05000374/2015008, November 18, 2015 (ML15323A064). |
| Exelon's LaSalle license renewal application identified the SSCs that fall within the scope of license renewal. The application is largely consistent with the Generic Aging Lessons Learned (GALL) Report (NUREG-1801). Deviations and exceptions are documented and justified.
| | : 8. U.S. Nuclear Regulatory Commission, NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, Revision 2, December 2010 (ML103490036). |
| Exelon will implement 46 AMPs for license renewal, comprised of 35 existing programs and 11 new programs. Nineteen of the 46 AMPs are consistent with the GALL Report without enhancements or exceptions. Nineteen AMPs are consistent with enhancements. Three AMPs are consistent with exceptions. Three AMPs are consistent with enhancements and exceptions. Two AMPs, Service Level III and Service Level III Augmented Coatings Monitoring and Maintenance Program, and Unit 2 Inspection of The American Society of Mechanical Engineers (ASME) Code Class 1 Small-Bore Piping Program, are plant-specific. The license renewal application includes six programs with exceptions to the GALL Report. We reviewed these programs (Flow-Accelerated Corrosion, Reactor Vessel Surveillance, Compressed Air Monitoring, Fire Water System, Reactor Head Closure Stud Bolting, and Water Chemistry). We conclude that the six GALL programs with exceptions are acceptable. The staff conducted license renewal audits and performed license renewal inspections at LaSalle. The audits verified the adequacy of the scoping and screening methodology for AMPs, the appropriateness of the aging management review, and the acceptability of the TLAAs. The inspection verified that the license renewal requirements are implemented appropriately. Both the inspection, and the report of that inspection, are thorough. Based on the audits, the inspection, and the staff reviews related to this license renewal application, the staff concluded in the final SER that the proposed activities will manage the effects of aging of SSCs identified in the application and that the intended functions of these SSCs will be maintained during the period of extended operation. The staff concluded that Exelon has demonstrated that the effects of aging at LaSalle will be adequately managed so that the intended function(s) will be maintained consistent with the current licensing basis for the period of extended operation, as required by 10 CFR 54.21(a)(3).
| | : 9. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.188, Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses, Revision 1, September 2005 (ML082950585). |
| | Distribution: |
| | See next page Accession No:ML16200A156 Publicly Available (Y/N): Y Sensitive (Y/N): N If Sensitive, which category? |
| | Viewing Rights: NRC Users or ACRS only or See restricted distribution OFFICE ACRS SUNSI ACRS ACRS ACRS Review NAME KHoward KHoward MBanks AValentin DBley DATE 7/18/16 7/18/16 7/18/16 7/18/16 7/18/16 OFFICIAL RECORD COPY |
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| Two open items were resolved between our subcommittee meeting on April 19, 2016, and our final review on July 6, 2016. The open items pertained to 1) enhanced visual testing examination coverage and 2) limited volumetric examination coverage. Resolution of the open items is as follows.
| | 3 Letter to the Honorable Stephen G. Burns, Chairman, NRC, from Dennis C. Bley, Chairman, ACRS, dated July 18, 2016 |
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| 3 EVT-1 Examination Coverage - BWR Vessel ID Attachment Welds Aging Management Program This item addresses changes to the BWR Vessel Internals Program (BWRVIP) guidance for EVT-1 viewing angle limitation that reduced effective examination coverage. Coverage requirements were not specified. The staff's concern was the program's ability to credit EVT-1s with 0% coverage; therefore, the staff raised the question of program adequacy. Exelon provided information to the NRC on February 25, 2016, in response to Request for Additional Information B.2.1.4-1 that 1) revised the procedure to eliminate the possibility that EVT-1 weld exam coverage of 0% could be acceptable and 2) communicated that visual inspections are performed of entire accessible Vessel ID attachment welds by a certified nondestructive examination examiner. EVT-1 examination cover age is maximized, consistent with BWRVIP-48-A and BWRVIP-03 guidance.
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| Limited Volumetric Exam Coverage - BWR Stress Corrosion Cracking Aging Management Program This item addresses examination coverage for augmented weld inspections. The staff was concerned that program effectiveness could not be assured without documented bases for crediting limited weld inspections. Exelon provided information to the NRC on February 25, 2016, stating that 90% examination coverage is considered the minimum acceptable examination coverage, without evaluation, during the period of extended operation. If examination coverage is less than 90%, procedures require action to maximize the extent of examination coverage. In addition, if the examinations with less than 90% coverage are required to meet ASME Code Section XI requirements, a relief request is required. Exelon changed procedures for examinations that are required to meet the AMP, but not to meet ASME code requirements. The new procedures require an engineering technical evaluation equivalent to a
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| relief request.
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| We agree with the staff that there are no issues related to the matters described in 10 CFR 54.29(a) (1) and (a) (2) that preclude renewal of the operating licenses for LaSalle. The programs established and committed to by Exelon provide reasonable assurance that LaSalle can be operated in accordance with its current licensing basis for the period of extended operation without undue risk to the health and safety of the public. The Exelon application for renewal of the operating licenses for LaSalle, Units 1 and 2 should be approved.
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| Sincerely,
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| /RA/
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| Dennis C. Bley Chairman 3 REFERENCES
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| : 1. Exelon Generation Company, LLC, LaSalle County Station, Units 1 and 2, "Application for Renewed Operating Licenses," December 9, 2014 (ML14343A840).
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| : 2. U.S. Nuclear Regulatory Commission, "Safety Evaluation Report Related to the License Renewal of LaSalle County Station, Units 1 and 2," June 2016 (ML16126A503).
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| : 3. U.S. Nuclear Regulatory Commission, "Safety Evaluation Report with Open items Related to the License Renewal of LaSalle County Station, Units 1 and 2," February
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| 2016 (ML16053A439).
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| : 4. U.S. Nuclear Regulatory Commission, NUREG 1801, "Generic Aging Lessons Learned (GALL) Report," Revision 2, December 2010 (ML103490041).
| |
| : 5. U.S. Nuclear Regulatory Commission , "Aging Management Programs Audit Report Regarding LaSalle County Station, Units 1 and 2 (TAC NOS. MF5347 and MF5346),"
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| September 22, 2015 (ML15196A115).
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| : 6. U.S. Nuclear Regulatory Commission, "Scoping and Screening Methodology Audit Report Regarding LaSalle County Station, Units 1 and 2 (TAC NOS. MF5347 and MF5346)," May 8, 2015 (ML15104A782).
| |
| : 7. U.S. Nuclear Regulatory Commission, "LaSalle County Station, Units 1 and 2 License Renewal Scoping, Screening, and Aging Management Inspection Report 05000373/2015008; 05000374/2015008," November 18, 2015 (ML15323A064).
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| : 8. U.S. Nuclear Regulatory Commission, NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants," Revision 2, December 2010 (ML103490036).
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| : 9. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.188, "Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses," Revision 1, September 2005 (ML082950585).
| |
| Distribution:
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| See next page Accession No:ML16200A156 Publicly Available (Y/N):
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| Y Sensitive (Y/N): N If Sensitive, which category?
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| Viewing Rights:
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| NRC Users or ACRS only or See restricted distribution OFFICE ACRS SUNSI Review ACRS ACRS ACRS NAME KHoward KHoward MBanks AValentin DBley DATE 7/18/16 7/18/16 7/18/16 7/18/16 7/18/16 OFFICIAL RECORD COPY 3 Letter to the Honorable Stephen G. Burns, Chairman, NRC, from Dennis C. Bley, Chairman, ACRS, dated July 18, 2016
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| ==SUBJECT:== | | ==SUBJECT:== |
| REPORT ON THE SAFETY ASPECTS OF THE LICENSE RENEWAL APPLICATION OF THE LASALLE COUNTY STATION, UNITS 1 AND 2 | | REPORT ON THE SAFETY ASPECTS OF THE LICENSE RENEWAL APPLICATION OF THE LASALLE COUNTY STATION, UNITS 1 AND 2 Distribution: |
| | | ACRS Staff ACRS Members ABates RidsSECYMailCenter RidsEDOMailCenter RidsNMSSOD RidsNSIROD RidsFSMEOD RidsRESOD RidsOIGMailCenter RidsOGCMailCenter RidsOCAAMailCenter RidsOCAMailCenter RidsNRROD RidsNROOD RidsOPAMail RidsRGN1MailCenter RidsRGN2MailCenter RidsRGN3MailCenter RidsRGN4MailCenter}} |
| Distribution: ACRS Staff ACRS Members ABates RidsSECYMailCenter RidsEDOMailCenter RidsNMSSOD RidsNSIROD RidsFSMEOD RidsRESOD | |
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| RidsOIGMailCenter | |
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| RidsOGCMailCenter RidsOCAAMailCenter RidsOCAMailCenter RidsNRROD | |
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| RidsNROOD RidsOPAMail RidsRGN1MailCenter RidsRGN2MailCenter RidsRGN3MailCenter RidsRGN4MailCenter}} | |
Letter Sequence Other |
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Results
Other: ML15005A480, ML15089A353, ML15104A317, ML15106A392, ML15106A812, ML15132A674, ML15195A341, ML15195A342, ML16019A174, ML16200A156, ML16204A236, ML16224A786, ML16264A222, ML16299A103, RS-15-179, Hard Copies of Responses Sheets Plus Other Relevant Documents - Part 3 of 3, RS-15-230, Final, Impingement and Entrainment Characterization Study
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MONTHYEARML15005A4742015-01-0707 January 2015
Notice of Intent to Prepare an Environmental Impact Statement and Conduct Scoping Process for LaSalle County Station, Units 1 and 2
Project stage: Request
ML15005A4802015-01-27027 January 2015
Notice of Intent to Prepare an Environmental Impact Statement and Conduct Scoping Process for LaSalle County, Units 1 and 2
Project stage: Other
ML15104A3172015-02-0303 February 2015
Comment (2) of Adam Kinzinger on License Renewal Application of LaSalle County Generating Station
Project stage: Other
ML15062A3642015-03-0303 March 2015
Environmental Scoping Briefing for March 10th Meetings
Project stage: Request
ML15089A5802015-03-10010 March 2015
Transcript of Public Meeting Re License Renewal Application of LaSalle, Units 1 and 2, Evening Session, March 10, 2015, Pages 1-55
Project stage: Meeting
ML15083A5382015-03-10010 March 2015
Transcript of Public Meeting Re License Renewal Application of LaSalle, Units 1 and 2, Afternoon Session, March 10, 2015, Pages 1-63
Project stage: Meeting
ML15089A3532015-03-12012 March 2015
Comment (1) of Nelson Dewey on LaSalle License Renewal Application Environmental Review
Project stage: Other
ML15083A5462015-03-31031 March 2015
Requests for Additional Information for the Environmental Review of LaSalle County Station, Units 1 and 2, License Renewal Application (TAC Nos. MF5567 and MF5568)
Project stage: RAI
ML15091A3292015-04-0101 April 2015
March 10, 2015, Public Scoping Meetings for Environmental Review of LaSalle County Station (LSCS) Units 1 and 2, License Renewal Application
Project stage: Meeting
ML15106A8122015-04-24024 April 2015
04/07-08/2015 Summary of Severe Accidents Mitigation Alternatives Audit for LaSalle County Station, Units 1 and 2 (TAC Nos. MF5567 and MF5568)
Project stage: Other
ML15106A3922015-04-28028 April 2015
License Renewal Environmental Site Audit Regarding Lasalle County Station, Units 1 and 2, (TAC Nos. MF5567 and MF5568)
Project stage: Other
ML15114A1022015-04-30030 April 2015
Requests for Additional Information on the LaSalle County Station Units 1 and 2 (LSCS) Analysis of Severe Accident Mitigation Alternatives
Project stage: RAI
ML15114A3202015-04-30030 April 2015
Request for Additional Information on Severe Accident Mitigation Alternatives Regarding the LaSalle County Station, Units 1 and 2, License Renewal Application Environmental Review
Project stage: RAI
ML15105A3812015-05-0404 May 2015
Environmental Audit Plan
Project stage: Request
ML15105A3662015-05-0404 May 2015
Environmental Audit Needs List
Project stage: Request
ML15132A6742015-05-20020 May 2015
Summary of the License Renewal Environmental Audit for LaSalle County Station, Units 1 and 2 (TAC Nos. MF5567 and MF5568)
Project stage: Other
ML15139A5862015-05-22022 May 2015
Request for Additional Information Regarding the LaSalle County Station, Units 1 and 2, License Renewal Application Environmental Review
Project stage: RAI
ML15135A5222015-05-22022 May 2015
Request for Additional Information Regarding the Lasalle County Station, Units 1 and 2, License Renewal Application Environmental Review (TAC Nos. MF5567 and MF5568)
Project stage: RAI
ML15195A3402015-07-0202 July 2015
Response to NRC Request for Additional Information, Dated May 22, 2015 Regarding License Renewal Application, Environmental Review
Project stage: Response to RAI
ML15195A3422015-07-0202 July 2015
Index for Responses to NRC License Renewal Environmental Review Requests for Additional Information - Part 2 of 3
Project stage: Other
ML15195A3672015-07-0202 July 2015
Response to NRC Request for Additional Information, Dated May 22, 2015 Regarding License Renewal Application, Environmental Review, AQ-01 on Aquatic Ecology
Project stage: Response to RAI
ML15195A3412015-07-0202 July 2015
Index for Responses to NRC License Renewal Environmental Review Requests for Additional Information - Part 1 of 3
Project stage: Other
ML15195A3522015-07-0202 July 2015
Response to NRC Request for Additional Information, Dated May 22, 2015 Regarding License Renewal Application, Environmental Review, MA-08 on Meteorology, Air Quality & Noise
Project stage: Response to RAI
ML15195A3492015-07-0202 July 2015
Response to NRC Request for Additional Information, Dated May 22, 2015 Regarding License Renewal Application, Environmental Review, MA-06 on Meteorology, Air Quality & Noise
Project stage: Response to RAI
ML15195A3462015-07-0202 July 2015
Response to NRC Request for Additional Information, Dated May 22, 2015 Regarding License Renewal Application, Environmental Review, MA-03 on Meteorology, Air Quality & Noise
Project stage: Response to RAI
ML15195A3452015-07-0202 July 2015
Response to NRC Request for Additional Information, Dated May 22, 2015 Regarding License Renewal Application, Environmental Review, MA-02 on Meteorology, Air Quality & Noise
Project stage: Response to RAI
RS-15-179, Hard Copies of Responses Sheets Plus Other Relevant Documents - Part 3 of 32015-07-0202 July 2015
Hard Copies of Responses Sheets Plus Other Relevant Documents - Part 3 of 3
Project stage: Other
ML15195A3502015-07-0202 July 2015
Response to NRC Request for Additional Information, Dated May 22, 2015 Regarding License Renewal Application, Environmental Review, MA-07 on Meteorology, Air Quality & Noise
Project stage: Response to RAI
ML15195A3472015-07-0202 July 2015
Response to NRC Request for Additional Information, Dated May 22, 2015 Regarding License Renewal Application, Environmental Review, MA-04 on Meteorology, Air Quality & Noise
Project stage: Response to RAI
ML15195A3542015-07-0202 July 2015
Response to NRC Request for Additional Information, Dated May 22, 2015 Regarding License Renewal Application, Environmental Review, MA-10 on Meteorology, Air Quality & Noise
Project stage: Response to RAI
ML15195A3532015-07-0202 July 2015
Response to NRC Request for Additional Information, Dated May 22, 2015 Regarding License Renewal Application, Environmental Review, MA-09 on Meteorology, Air Quality & Noise
Project stage: Response to RAI
ML15195A3482015-07-0202 July 2015
Response to NRC Request for Additional Information, Dated May 22, 2015 Regarding License Renewal Application, Environmental Review, MA-05 on Meteorology, Air Quality & Noise
Project stage: Response to RAI
ML15195A3442015-07-0202 July 2015
Response to NRC Request for Additional Information, Dated May 22, 2015 Regarding License Renewal Application, Environmental Review, MA-01 on Meteorology, Air Quality & Noise
Project stage: Response to RAI
ML15147A3802015-07-0202 July 2015
Issuance of Scoping Summary Report Associated with the LaSalle County Station, Units 1 and 2, License Renewal Application Environmental Review
Project stage: Approval
RS-15-230, Final, Impingement and Entrainment Characterization Study2015-08-27027 August 2015
Final, Impingement and Entrainment Characterization Study
Project stage: Other
ML15243A2032015-08-27027 August 2015
LaSalle County, Units 1 and 2 - Supplement to Enclosure B of Exelon Generation'S Response to NRC Request for Additional Information, Dated May 22, 2015, Regarding License Renewal Application, Environmental Review
Project stage: Response to RAI
ML16036A3482016-02-0505 February 2016
Maintenance of Draft Supplemental Environmental Impact Statement at the Seneca Public Library in Regards to the Review of the LaSalle County Station License Renewal Application (TAC Nos. MF5567 and MF5568)
Project stage: Draft Approval
ML16019A1742016-02-0808 February 2016
Dseis NOA to EPA Region 5
Project stage: Other
ML16019A1462016-02-0808 February 2016
Notice of Availability of the Draft Plant-Specific Supplement 57 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding LaSalle County Station, Units 1 and 2 (TAC Nos. MF5567 and MF5568)
Project stage: Draft Other
ML16019A1062016-02-0808 February 2016
FRN Dseis - Adm Oked - OGC NLO
Project stage: Request
ML16050A4932016-02-13013 February 2016
Maintenance of Draft Supplemental Environmental Impact Statement at the Seneca Public Library in Regards to the Review of the LaSalle County Station License Renewal Application
Project stage: Draft Approval
ML16033A1032016-02-29029 February 2016
NUREG-1437 Dfc, Supp 57, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding LaSalle County Station, Units 1 and 2.
Project stage: Acceptance Review
RS-16-144, Response to Request for Additional Information on Severe Accident Mitigation Alternatives for License Renewal Environmental Review Dated July 6, 20162016-07-11011 July 2016
Response to Request for Additional Information on Severe Accident Mitigation Alternatives for License Renewal Environmental Review Dated July 6, 2016
Project stage: Response to RAI
ML16200A1562016-07-18018 July 2016
Report on the Safety Aspects of the License Renewal Application of the LaSalle County Station, Units 1 and 2
Project stage: Other
ML16224A7862016-08-26026 August 2016
Notice of Availability of the Final Plant-Specific Supplement 57 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding LaSalle County Station, Units 1 and 2 (TAC Nos. MF5567 and MF5568)
Project stage: Other
ML16204A2362016-08-26026 August 2016
Notice of Availability of the Final Plant-Specific Supplement 57 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding LaSalle County Station, Units 1 and 2 (TAC No. MF5567 & MF5568)
Project stage: Other
ML16264A2222016-10-19019 October 2016
Record of Decision for License Renewal
Project stage: Other
ML16299A1032016-10-24024 October 2016
Letter to Ruth Thomas Transmitting Record of Decision on LaSalle County Station License Renewal Application
Project stage: Other
2015-05-22
[Table View] |
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Category:Letter
MONTHYEARRS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024
Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
05000373/LER-2023-001-01, Air Circuit Breaker (Acb) Mechanically Operated Contacts (MOC) Switch Failed to Actuate2024-10-0909 October 2024
Air Circuit Breaker (Acb) Mechanically Operated Contacts (MOC) Switch Failed to Actuate
ML24275A2442024-10-0303 October 2024
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing
IR 05000373/20244012024-09-27027 September 2024
County Station – Security Baseline Inspection Report 05000373/2024401 and 05000374/2024401
ML24263A2062024-09-19019 September 2024
Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for LaSalle County Station - Holtec MPC-68MCBS
ML24260A0492024-09-16016 September 2024
Operator Licensing Examination Approval - Lasalle County Station, Unit 1 and 2, September 2024
RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024
Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
ML24255A8642024-09-0606 September 2024
Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification
ML24249A1362024-09-0404 September 2024
EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21
IR 05000373/20240052024-08-29029 August 2024
Updated Inspection Plan and Assessment Follow-Up Letter for Lasalle County Station (Report 05000373/2024005; 05000374/2024005)
IR 05000373/20244022024-08-28028 August 2024
County Station - Cyber Security Inspection Report 05000373/2024402 and 05000374/2024402
ML24239A3972024-08-23023 August 2024
Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243
05000373/LER-2024-004-01, Emergency Diesel Generator Auto-Start and Load Due to Loss of System Auxiliary Transformer2024-08-22022 August 2024
Emergency Diesel Generator Auto-Start and Load Due to Loss of System Auxiliary Transformer
IR 05000373/20240022024-08-13013 August 2024
County Station - Integrated Inspection Report 05000373/2024002 and 05000374/2024002
ML24222A6772024-08-0909 August 2024
Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
IR 05000373/20244202024-08-0505 August 2024
County Station - Security Baseline Inspection Report 05000373 2024420 and 05000374 2024420
05000373/LER-2024-003, Supplement to Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded2024-07-31031 July 2024
Supplement to Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.3 Completion Time Exceeded
ML24208A0962024-07-25025 July 2024
57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification
RS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024
Nuclear Radiological Emergency Plan Document Revisions
ML24178A2522024-06-27027 June 2024
County Station – Acknowledgement of Response to NRC Inspection Report 05000373/2024001 and 05000374/2024001 and Disputed Non-Cited Violation
RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024
Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
IR 05000373/20240102024-05-29029 May 2024
County Station - Commercial Grade Dedication Inspection Report 05000373/2024010 and 05000374/2024010
ML24079A0762024-05-23023 May 2024
Issuance of Amendments to Adopt TSTF 264
ML24142A3352024-05-21021 May 2024
Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes
RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024
2023 Corporate Regulatory Commitment Change Summary Report
ML24131A1512024-05-13013 May 2024
County Station - Integrated Report 05000373/2024001 and 05000374/2024001
IR 05000373/20240012024-05-13013 May 2024
County Station - Integrated Report 05000373/2024001 and 05000374/2024001
RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024
Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024
Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests
ML24108A1562024-04-15015 April 2024
Updated Final Safety Analysis Report (Ufsar), Revision 26 and Fire Protection Report (Fpr), Revision 11
ML24103A2042024-04-12012 April 2024
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition
RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024
Constellation Energy Generation, LLC - Annual Property Insurance Status Report
ML24071A2122024-03-12012 March 2024
County Station - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection
IR 05000373/20230062024-02-28028 February 2024
Annual Assessment Letter for Lasalle County Station, Units 1 and 2 (Report 05000373/2023006; 05000374/2023006)
RS-24-014, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-02-22022 February 2024
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
ML24018A0682024-02-0909 February 2024
Issuance of Amendment Nos. 262 and 247 Revised Design Bases of Lower Downcomer Braces
ML24024A1332024-01-24024 January 2024
Confirmation of Initial License Examination
IR 05000373/20230042024-01-24024 January 2024
County Station - Integrated Inspection Report 05000373/2023004 and 05000374/2023004
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
2024-09-06
[Table view]
Category:Report
MONTHYEARRA24-008, Post-Outage Inservice Inspection (ISI) Summary Report2024-06-20020 June 2024
Post-Outage Inservice Inspection (ISI) Summary Report
RS-24-014, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-02-22022 February 2024
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
ML23181A1522023-06-30030 June 2023
Attachment 2 - LaSalle County Station Units 1 and 2, Pressure and Temperature Limits Report (PTLR) Up to 54 Effective Full-Power Years (Efpy), Revision 3
RS-23-066, Containment Post-Tensioning System Inservice Inspection Basis for Proposed Extension of Examination Interval Technical Report2023-05-0303 May 2023
Containment Post-Tensioning System Inservice Inspection Basis for Proposed Extension of Examination Interval Technical Report
RA22-060, Regulatory Commitment Change Summary Report2022-11-30030 November 2022
Regulatory Commitment Change Summary Report
ML22332A4552022-11-10010 November 2022
Attachment 7 - BWRVIP-135, Revision 4: BWR Vessel Internals Project Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations (Non-Proprietary Version)
ML22332A4542022-11-10010 November 2022
Attachment 6 - LaSalle County Generating Station Units 1 and 2 Pressure and Temperature Limits Report (PTLR) for 54 Effective Full-Power Years (EFPY) (Non-Proprietary)
NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022
Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits
RS-22-018, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station2022-02-22022 February 2022
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station
RS-21-115, Supplemental Information for License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical Specifications 4.3.1 and 5.6.52021-11-0404 November 2021
Supplemental Information for License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical Specifications 4.3.1 and 5.6.5
ML21265A5582021-06-30030 June 2021
Attachment 5: Appendix C, NEI 12-16 Criticality Analysis Checklist
RA21-016, Netco Rack Insert 10-year Surveillance Report2021-04-15015 April 2021
Netco Rack Insert 10-year Surveillance Report
RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021
Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping
ML20303A1752020-10-23023 October 2020
Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting
RS-20-133, Response to Request for Additional Information Re License Amendment Request to Renewed Facility Operating Licenses to Adopt 10 CFR 50.692020-10-16016 October 2020
Response to Request for Additional Information Re License Amendment Request to Renewed Facility Operating Licenses to Adopt 10 CFR 50.69
ML20085F8612020-03-24024 March 2020
Corrected Drawing for One-Line Electric Power Supply for Lasalle Hardened Containment Vent System (HCVS) Final Integrated Plan (FIP)
RA20-015, Triennial Chlorine Survey Report2020-03-20020 March 2020
Triennial Chlorine Survey Report
RS-20-024, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2020-03-0909 March 2020
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
ML19228A0232019-08-15015 August 2019
Proposed Alternative to Utilize Code Case N-879
RA19-005, Regulatory Commitment Change Summary Report2019-01-14014 January 2019
Regulatory Commitment Change Summary Report
RA18-110, Submittal of 2017 Regulatory Commitment Change Summary Report2018-12-27027 December 2018
Submittal of 2017 Regulatory Commitment Change Summary Report
RS-18-131, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2018-12-14014 December 2018
Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions
ML18024A2772018-08-16016 August 2018
Lessons Learned from Us NRC Response to the February 2017 LaSalle County Station Unit 2 High Pressure Core Spray Injection Valve Failure
RA17-072, Post Accident Monitoring Report2017-08-0202 August 2017
Post Accident Monitoring Report
RA17-069, Post Accident Monitoring Report2017-07-21021 July 2017
Post Accident Monitoring Report
RS-17-025, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-03-0808 March 2017
Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal
ML16355A4182017-01-11011 January 2017
Flood Hazard Mitigation Strategies Assessment
RA16-092, Regulatory Commitment Change Summary Report2016-12-27027 December 2016
Regulatory Commitment Change Summary Report
RS-16-182, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-10-28028 October 2016
Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal
ML16305A2962016-10-27027 October 2016
0000-0163-8881-R0-NP, Revision 0, Exelon Nuclear LaSalle County Generating Station Units 1 & 2 Pool Swell Response.
ML16167A5022016-09-0606 September 2016
UFSAR, Rev 22, Chap 09 Figures Part 12 of 14 - Redacted
ML16167A4462016-09-0606 September 2016
MF7633 and MF7634, UFSAR, Las Fpr Rev._Redacted
RS-16-125, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-08-31031 August 2016
Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
ML16224A7862016-08-26026 August 2016
Notice of Availability of the Final Plant-Specific Supplement 57 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding LaSalle County Station, Units 1 and 2 (TAC Nos. MF5567 and MF5568)
ML16200A1562016-07-18018 July 2016
Report on the Safety Aspects of the License Renewal Application of the LaSalle County Station, Units 1 and 2
RS-15-300, Phase 1 (Updated) and Phase 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident..2015-12-16016 December 2015
Phase 1 (Updated) and Phase 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident..
RA15-075, Transmittal of the 2014 Regulatory Commitment Change Summary Report2015-11-20020 November 2015
Transmittal of the 2014 Regulatory Commitment Change Summary Report
ML15107A1542015-04-21021 April 2015
Final Accident Sequence Precursor Analysis for the April 17, 2013, Dual Unit Loss of Offsite Power
RS-15-004, County Station Introduction of Lead Use Assemblies2015-01-20020 January 2015
County Station Introduction of Lead Use Assemblies
ML14352A1902014-12-18018 December 2014
7491-318563-HAO-1, Rev. 2, LaSalle Requested Documents
RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014
Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1
ML14177A8592014-06-30030 June 2014
Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident
ML14176A9612014-06-24024 June 2014
Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014
RS-14-054, LaSalle, Unit 1, Supplemental Information Supporting License Amendment Request to Revise Reactor Coolant System (RCS) Pressure and Temperature (Pit) Curves2014-02-26026 February 2014
LaSalle, Unit 1, Supplemental Information Supporting License Amendment Request to Revise Reactor Coolant System (RCS) Pressure and Temperature (Pit) Curves
ML14057A5492014-02-26026 February 2014
Supplemental Information Supporting License Amendment Request to Revise Reactor Coolant System (RCS) Pressure and Temperature (Pit) Curves
ML14030A2232014-02-21021 February 2014
Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)
ML14042A3252014-02-19019 February 2014
Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for LaSalle County Station, Units 1 and 2, TAC Nos.: MF1121 and MF1122
ML13358A3652013-12-20020 December 2013
Attachment 5: LaSalle County Station, Unit 1, Pressure/Temperature Limits Report
ML13344A9822013-12-0909 December 2013
2012 Regulatory Commitment Change Summary Report
ML13282A3502013-10-0404 October 2013
Final Report, Assessment of Wind Speeds Over the LaSalle County Station Ultimate Heat Sink.
2024-06-20
[Table view]
Category:Miscellaneous
MONTHYEARRA24-008, Post-Outage Inservice Inspection (ISI) Summary Report2024-06-20020 June 2024
Post-Outage Inservice Inspection (ISI) Summary Report
RS-24-014, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-02-22022 February 2024
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RA22-060, Regulatory Commitment Change Summary Report2022-11-30030 November 2022
Regulatory Commitment Change Summary Report
ML21265A5582021-06-30030 June 2021
Attachment 5: Appendix C, NEI 12-16 Criticality Analysis Checklist
RA21-016, Netco Rack Insert 10-year Surveillance Report2021-04-15015 April 2021
Netco Rack Insert 10-year Surveillance Report
ML20303A1752020-10-23023 October 2020
Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting
RA20-015, Triennial Chlorine Survey Report2020-03-20020 March 2020
Triennial Chlorine Survey Report
RS-20-024, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2020-03-0909 March 2020
Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
RA19-005, Regulatory Commitment Change Summary Report2019-01-14014 January 2019
Regulatory Commitment Change Summary Report
RA18-110, Submittal of 2017 Regulatory Commitment Change Summary Report2018-12-27027 December 2018
Submittal of 2017 Regulatory Commitment Change Summary Report
RA17-072, Post Accident Monitoring Report2017-08-0202 August 2017
Post Accident Monitoring Report
RA17-069, Post Accident Monitoring Report2017-07-21021 July 2017
Post Accident Monitoring Report
RS-17-025, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-03-0808 March 2017
Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal
ML16355A4182017-01-11011 January 2017
Flood Hazard Mitigation Strategies Assessment
RA16-092, Regulatory Commitment Change Summary Report2016-12-27027 December 2016
Regulatory Commitment Change Summary Report
RS-16-182, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-10-28028 October 2016
Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal
ML16305A2962016-10-27027 October 2016
0000-0163-8881-R0-NP, Revision 0, Exelon Nuclear LaSalle County Generating Station Units 1 & 2 Pool Swell Response.
RS-16-125, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-08-31031 August 2016
Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
ML16224A7862016-08-26026 August 2016
Notice of Availability of the Final Plant-Specific Supplement 57 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding LaSalle County Station, Units 1 and 2 (TAC Nos. MF5567 and MF5568)
ML16200A1562016-07-18018 July 2016
Report on the Safety Aspects of the License Renewal Application of the LaSalle County Station, Units 1 and 2
RS-15-300, Phase 1 (Updated) and Phase 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident..2015-12-16016 December 2015
Phase 1 (Updated) and Phase 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident..
RA15-075, Transmittal of the 2014 Regulatory Commitment Change Summary Report2015-11-20020 November 2015
Transmittal of the 2014 Regulatory Commitment Change Summary Report
ML14352A1902014-12-18018 December 2014
7491-318563-HAO-1, Rev. 2, LaSalle Requested Documents
ML14177A8592014-06-30030 June 2014
Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident
ML13344A9822013-12-0909 December 2013
2012 Regulatory Commitment Change Summary Report
IR 05000456/20132022013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000289/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000272/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
ML13008A2192013-01-31031 January 2013
U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000254/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000277/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000219/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000352/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000373/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000237/20132022013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000461/20132012013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
IR 05000454/20132022013-01-31031 January 2013
Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee
ML12353A2172012-11-0101 November 2012
12Q0108.50-R-002, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the LaSalle County Station, Unit 2, Part 9 of 16
ML12353A2232012-11-0101 November 2012
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UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 July 18, 2016 The Honorable Stephen G. Burns Chairman U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
REPORT ON THE SAFETY ASPECTS OF THE LICENSE RENEWAL APPLICATION OF THE LASALLE COUNTY STATION, UNITS 1 AND 2
Dear Chairman Burns:
During the 635th meeting of the Advisory Committee on Reactor Safeguards (ACRS), July 6 - 8, 2016, we completed our review of the license renewal application for the LaSalle County Station, Units 1 and 2 (LaSalle) and the final safety evaluation report (SER) prepared by the NRC staff. Our Subcommittee on Plant License Renewal reviewed this matter during a meeting on April 19, 2016. During these reviews, we had the benefit of discussions with representatives of the NRC staff and the Exelon Generation Company, LLC (Exelon or the applicant). We also had the benefit of the referenced documents. This report fulfills the requirement of 10 CFR 54.25 that the ACRS review and report on all license renewal applications.
CONCLUSION AND RECOMMENDATION
- 1. The programs established and committed to by Exelon to manage age-related degradation provide reasonable assurance that LaSalle can be operated in accordance with its current licensing bases for the period of extended operation without undue risk to the health and safety of the public.
- 2. Exelons application for renewal of the operating licenses for LaSalle should be approved.
BACKGROUND LaSalle is located approximately 55 miles southwest of Chicago, Illinois. Units 1 and 2 are of a boiling water reactor (BWR) Type 5 (BWR/5) design. Each primary containment is a Mark II type, safety-related seismic Category I structure consisting of a steel dome head and post-tensioned concrete wall standing on a base mat of conventionally reinforced concrete. General Electric provided the nuclear steam supply system, and Sargent & Lundy designed and constructed the balance of the plant. Each unit has a licensed power output of 3,546 megawatts thermal, with a gross electrical output of approximately 1,207 megawatts. The NRC issued the construction permits (CPRR-99 and CPRR-100, respectively) for Units 1 and 2 on September 7, 1973. The NRC issued the operating licenses for Unit 1 and Unit 2 on April 17, 1982, and December 16, 1983, respectively.
2 In this application, Exelon requests renewal of the operating licenses (Facility Operating License Nos. NPF-11 and NPF-18) for a period of 20 years beyond the current expiration date of April 17, 2022, for Unit 1, and December 16, 2023, for Unit 2.
DISCUSSION In its final SER, dated June 2016, the staff documented its review of the license renewal application and other information submitted by the applicant and obtained through staff audits and inspections at the plant sites. The staff reviewed the completeness of the identification of structures, systems, and components (SSCs) that are within the scope of license renewal; the integrated plant assessment process; the identification of plausible aging mechanisms associated with passive, long-lived components; the adequacy of the Aging Management Programs (AMPs); and identification and assessment of Time-Limited Aging Analyses (TLAAs) requiring review.
Exelons LaSalle license renewal application identified the SSCs that fall within the scope of license renewal. The application is largely consistent with the Generic Aging Lessons Learned (GALL) Report (NUREG-1801). Deviations and exceptions are documented and justified.
Exelon will implement 46 AMPs for license renewal, comprised of 35 existing programs and 11 new programs. Nineteen of the 46 AMPs are consistent with the GALL Report without enhancements or exceptions. Nineteen AMPs are consistent with enhancements. Three AMPs are consistent with exceptions. Three AMPs are consistent with enhancements and exceptions.
Two AMPs, Service Level III and Service Level III Augmented Coatings Monitoring and Maintenance Program, and Unit 2 Inspection of The American Society of Mechanical Engineers (ASME) Code Class 1 Small-Bore Piping Program, are plant-specific.
The license renewal application includes six programs with exceptions to the GALL Report. We reviewed these programs (Flow-Accelerated Corrosion, Reactor Vessel Surveillance, Compressed Air Monitoring, Fire Water System, Reactor Head Closure Stud Bolting, and Water Chemistry). We conclude that the six GALL programs with exceptions are acceptable.
The staff conducted license renewal audits and performed license renewal inspections at LaSalle. The audits verified the adequacy of the scoping and screening methodology for AMPs, the appropriateness of the aging management review, and the acceptability of the TLAAs. The inspection verified that the license renewal requirements are implemented appropriately. Both the inspection, and the report of that inspection, are thorough. Based on the audits, the inspection, and the staff reviews related to this license renewal application, the staff concluded in the final SER that the proposed activities will manage the effects of aging of SSCs identified in the application and that the intended functions of these SSCs will be maintained during the period of extended operation. The staff concluded that Exelon has demonstrated that the effects of aging at LaSalle will be adequately managed so that the intended function(s) will be maintained consistent with the current licensing basis for the period of extended operation, as required by 10 CFR 54.21(a)(3).
Two open items were resolved between our subcommittee meeting on April 19, 2016, and our final review on July 6, 2016. The open items pertained to 1) enhanced visual testing examination coverage and 2) limited volumetric examination coverage. Resolution of the open items is as follows.
3 EVT-1 Examination Coverage - BWR Vessel ID Attachment Welds Aging Management Program This item addresses changes to the BWR Vessel Internals Program (BWRVIP) guidance for EVT-1 viewing angle limitation that reduced effective examination coverage. Coverage requirements were not specified. The staffs concern was the programs ability to credit EVT-1s with 0% coverage; therefore, the staff raised the question of program adequacy. Exelon provided information to the NRC on February 25, 2016, in response to Request for Additional Information B.2.1.4-1 that 1) revised the procedure to eliminate the possibility that EVT-1 weld exam coverage of 0% could be acceptable and 2) communicated that visual inspections are performed of entire accessible Vessel ID attachment welds by a certified nondestructive examination examiner. EVT-1 examination coverage is maximized, consistent with BWRVIP A and BWRVIP-03 guidance.
Limited Volumetric Exam Coverage - BWR Stress Corrosion Cracking Aging Management Program This item addresses examination coverage for augmented weld inspections. The staff was concerned that program effectiveness could not be assured without documented bases for crediting limited weld inspections. Exelon provided information to the NRC on February 25, 2016, stating that 90% examination coverage is considered the minimum acceptable examination coverage, without evaluation, during the period of extended operation. If examination coverage is less than 90%, procedures require action to maximize the extent of examination coverage. In addition, if the examinations with less than 90% coverage are required to meet ASME Code Section XI requirements, a relief request is required. Exelon changed procedures for examinations that are required to meet the AMP, but not to meet ASME code requirements. The new procedures require an engineering technical evaluation equivalent to a relief request.
We agree with the staff that there are no issues related to the matters described in 10 CFR 54.29(a) (1) and (a) (2) that preclude renewal of the operating licenses for LaSalle. The programs established and committed to by Exelon provide reasonable assurance that LaSalle can be operated in accordance with its current licensing basis for the period of extended operation without undue risk to the health and safety of the public. The Exelon application for renewal of the operating licenses for LaSalle, Units 1 and 2 should be approved.
Sincerely,
/RA/
Dennis C. Bley Chairman
3 REFERENCES
- 1. Exelon Generation Company, LLC, LaSalle County Station, Units 1 and 2, Application for Renewed Operating Licenses, December 9, 2014 (ML14343A840).
- 2. U.S. Nuclear Regulatory Commission, Safety Evaluation Report Related to the License Renewal of LaSalle County Station, Units 1 and 2, June 2016 (ML16126A503).
- 3. U.S. Nuclear Regulatory Commission, Safety Evaluation Report with Open items Related to the License Renewal of LaSalle County Station, Units 1 and 2, February 2016 (ML16053A439).
- 4. U.S. Nuclear Regulatory Commission, NUREG 1801, Generic Aging Lessons Learned (GALL) Report, Revision 2, December 2010 (ML103490041).
- 5. U.S. Nuclear Regulatory Commission, Aging Management Programs Audit Report Regarding LaSalle County Station, Units 1 and 2 (TAC NOS. MF5347 and MF5346),
September 22, 2015 (ML15196A115).
- 6. U.S. Nuclear Regulatory Commission, Scoping and Screening Methodology Audit Report Regarding LaSalle County Station, Units 1 and 2 (TAC NOS. MF5347 and MF5346), May 8, 2015 (ML15104A782).
- 7. U.S. Nuclear Regulatory Commission, LaSalle County Station, Units 1 and 2 License Renewal Scoping, Screening, and Aging Management Inspection Report 05000373/2015008; 05000374/2015008, November 18, 2015 (ML15323A064).
- 8. U.S. Nuclear Regulatory Commission, NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, Revision 2, December 2010 (ML103490036).
- 9. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.188, Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses, Revision 1, September 2005 (ML082950585).
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Viewing Rights: NRC Users or ACRS only or See restricted distribution OFFICE ACRS SUNSI ACRS ACRS ACRS Review NAME KHoward KHoward MBanks AValentin DBley DATE 7/18/16 7/18/16 7/18/16 7/18/16 7/18/16 OFFICIAL RECORD COPY
3 Letter to the Honorable Stephen G. Burns, Chairman, NRC, from Dennis C. Bley, Chairman, ACRS, dated July 18, 2016
SUBJECT:
REPORT ON THE SAFETY ASPECTS OF THE LICENSE RENEWAL APPLICATION OF THE LASALLE COUNTY STATION, UNITS 1 AND 2 Distribution:
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