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Category:Report
MONTHYEARLG-24-109, CFR 50.59 and 10 CFR 72.48 Evaluation 24-Month Summary Report for the Period July 1, 2022 Through June 30, 20242024-11-0101 November 2024 CFR 50.59 and 10 CFR 72.48 Evaluation 24-Month Summary Report for the Period July 1, 2022 Through June 30, 2024 ML24180A1592024-06-18018 June 2024 EQ-EV-386-GLIM-NP, Revision 2, Comparison of Equipment Qualification Hardware Testing for Common Q Applications to Limerick Requirements ML24026A2962024-01-26026 January 2024 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System (PPS)- Syrs, . LG-23-059, Owners Activity Report (OAR-1) for Li2R 172023-08-10010 August 2023 Owners Activity Report (OAR-1) for Li2R 17 ML23177A2242023-06-26026 June 2023 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection . LG-22-101, Annual Commitment Change Summary Report2022-11-14014 November 2022 Annual Commitment Change Summary Report ML22224A1492022-08-15015 August 2022 Review of Limerick Generating Station Defense in Depth and Diversity Common Cause Failure Coping Analysis, WNA-AR-01074-GLIM-P, Revision 2, July 2022, and the Licensing Technical Report for the Limerick Generating Station Units 1&2 Digital 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 ML22046A0742022-02-14014 February 2022 Review of Limerick Generating Station Defense in Depth and Diversity Common Cause Failure Coping Analysis, WNA-AR-01074-GLIM-P, Rev 1. Without Attachment 3 Enclosure ML21070A4122021-03-11011 March 2021 Requesting Revision to License Condition in Appendix C in Renewed Facility Operating License ML21083A1712021-02-28028 February 2021 Attachment 3: Limerick Generating Station, Unit 2, 006N3997NP, Revision 1, High Burnup Lead Use Assembly (Hblua) Information Report February 2021 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 LG-20-105, Annual Commitment Change Summary Report2020-11-23023 November 2020 Annual Commitment Change Summary Report ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML20106E8282020-04-15015 April 2020 Submittal of Analytical Evaluation of Core Spray Injection Nozzle-to-Safe End Weld (N5A) ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 RS-18-051, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2018-06-0707 June 2018 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events ML18129A3342018-05-0404 May 2018 Corrosion Evaluation of the Limerick Unit 2 N-160 Reactor Vessel Nozzle Modification, Framatome Document No. 51-9271770-002 (Non-Proprietary) ML17255A0302017-09-12012 September 2017 Independent Spent Fuel Storage Installation, Registration of Use of Casks to Store Spent Fuel ML17152A3052017-06-0101 June 2017 N-16D Nozzle Repair - Submittal of Analytical Flaw Evaluation, Design Analysis, and Corrosion Evaluation (Rev. 1) ML17137A0682017-05-16016 May 2017 Proposed Relief Request Associated with Reactor Pressure Vessel Nozzle Repairs ML17131A1802017-05-11011 May 2017 Issuance of the Core Operating Limits Report (COLR) for Reload 14, Cycle 15 RS-16-177, High Frequency Supplement to Seismic Hazard Screening 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..2016-11-28028 November 2016 High Frequency Supplement to Seismic Hazard Screening 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.. ML16309A0172016-11-0404 November 2016 10 CFR 50.59 and 1 O CFR 72.48 Evaluation 24-Month Summary Report for the Period July 1, 2014 Through June 30, 2016 ML16307A0202016-11-0202 November 2016 Special Report - Accident Monitoring Instrumentation Inoperability 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 ML14199A4112014-07-18018 July 2014 Special Report - Seismic Monitoring Instrumentation Inoperability ML14148A2802014-06-17017 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 ML14133A0162014-05-13013 May 2014 ACE Attachment to NRC Chairman Macfarlane Letter of 3-31-14 ML14133A0222014-05-13013 May 2014 ACE Document Received at LIM Aam May 7, 2014 ML14058B1562014-04-14014 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14058B1202014-04-14014 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13357A3312014-01-0606 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Limerick Generating Station, Units 1 and 2, TAC Nos.: MF0847 and MF0848 RS-13-138, Updated Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Limerick Generating Station, Unit 2, Report No. RS-13-1382013-10-0707 October 2013 Updated Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Limerick Generating Station, Unit 2, Report No. RS-13-138 ML13284A1112013-10-0707 October 2013 Appendix AD - Area Walk-by Checklists (Awcs) ML13143A2562013-05-16016 May 2013 NRC Reply to ACE Questions Received March 21 and 27, 2013 RS-13-084, Response to March 12, 2012, Request for Information Per 10 CFR 50.45.(f) Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, Emergency..2013-04-30030 April 2013 Response to March 12, 2012, Request for Information Per 10 CFR 50.45.(f) Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, Emergency.. 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 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 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 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 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 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 RS-12-172, Company, Llc'S 180-day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-19019 November 2012 Company, Llc'S 180-day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident 2024-06-18
[Table view] Category:Miscellaneous
MONTHYEARLG-24-109, CFR 50.59 and 10 CFR 72.48 Evaluation 24-Month Summary Report for the Period July 1, 2022 Through June 30, 20242024-11-0101 November 2024 CFR 50.59 and 10 CFR 72.48 Evaluation 24-Month Summary Report for the Period July 1, 2022 Through June 30, 2024 LG-23-059, Owners Activity Report (OAR-1) for Li2R 172023-08-10010 August 2023 Owners Activity Report (OAR-1) for Li2R 17 LG-22-101, Annual Commitment Change Summary Report2022-11-14014 November 2022 Annual Commitment Change Summary Report ML21083A1712021-02-28028 February 2021 Attachment 3: Limerick Generating Station, Unit 2, 006N3997NP, Revision 1, High Burnup Lead Use Assembly (Hblua) Information Report February 2021 ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML17255A0302017-09-12012 September 2017 Independent Spent Fuel Storage Installation, Registration of Use of Casks to Store Spent Fuel ML17131A1802017-05-11011 May 2017 Issuance of the Core Operating Limits Report (COLR) for Reload 14, Cycle 15 ML16309A0172016-11-0404 November 2016 10 CFR 50.59 and 1 O CFR 72.48 Evaluation 24-Month Summary Report for the Period July 1, 2014 Through June 30, 2016 ML14199A4112014-07-18018 July 2014 Special Report - Seismic Monitoring Instrumentation Inoperability ML14148A2802014-06-17017 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 ML14133A0222014-05-13013 May 2014 ACE Document Received at LIM Aam May 7, 2014 ML14058B1562014-04-14014 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14058B1202014-04-14014 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident RS-13-138, Updated Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Limerick Generating Station, Unit 2, Report No. RS-13-1382013-10-0707 October 2013 Updated Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Limerick Generating Station, Unit 2, Report No. RS-13-138 ML13284A1112013-10-0707 October 2013 Appendix AD - Area Walk-by Checklists (Awcs) ML13143A2562013-05-16016 May 2013 NRC Reply to ACE Questions Received March 21 and 27, 2013 RS-13-084, Response to March 12, 2012, Request for Information Per 10 CFR 50.45.(f) Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, Emergency..2013-04-30030 April 2013 Response to March 12, 2012, Request for Information Per 10 CFR 50.45.(f) Recommendations of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Enclosure 5, Recommendation 9.3, Emergency.. 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 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 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 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 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 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 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 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 RS-12-172, Company, Llc'S 180-day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-19019 November 2012 Company, Llc'S 180-day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML12342A1142012-11-0606 November 2012 MPR-3796, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 9 of 12 ML12342A1022012-11-0606 November 2012 MPR-3801, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 13 of 13 ML12342A1032012-11-0606 November 2012 MPR-3796, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 1 of 12 ML12342A1042012-11-0606 November 2012 MPR-3796, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 2 of 12 ML12342A1052012-11-0606 November 2012 MPR-3796, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 3 of 12 ML12342A1062012-11-0606 November 2012 MPR-3796, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 4 of 12 ML12342A1072012-11-0606 November 2012 MPR-3796, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 5 of 12 ML12342A1102012-11-0606 November 2012 MPR-3796, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 6 of 12 ML12342A1122012-11-0606 November 2012 MPR-3796, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 7 of 12 ML12342A1132012-11-0606 November 2012 MPR-3796, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 8 of 12 ML12342A1152012-11-0606 November 2012 MPR-3796, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 10 of 12 ML12342A1162012-11-0606 November 2012 MPR-3796, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 11 of 12 ML12342A1172012-11-0606 November 2012 MPR-3796, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 12 of 12 ML12342A1182012-11-0606 November 2012 MPR-3801, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 1 of 13 ML12342A1192012-11-0606 November 2012 MPR-3801, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 2 of 13 ML12342A1212012-11-0606 November 2012 MPR-3801, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 3 of 13 ML12342A1222012-11-0606 November 2012 MPR-3801, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 4 of 13 ML12342A1232012-11-0606 November 2012 MPR-3801, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 5 of 13 ML12342A1242012-11-0606 November 2012 MPR-3801, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 6 of 13 ML12342A1252012-11-0606 November 2012 MPR-3801, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 7 of 13 2024-11-01
[Table view] |
Text
She=_ 1 of 2 Status: Y() N U Seismic Walkdown Checklist (SWC)Equipment ID No. 4OK2+ 10X 10 F Equip. Class1 2 (02) Transformers Equipment Description 4KV-480V Transformer Location:
Bldg. Reactor Floor El. -3. .3 Room, Area Room /fflW" .p E Enclosure Manufacturer, Model, Etc. (optional but recommended).
Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.
Additional space is provided at the end of this checklist for documenting other comments.Anchorarme
- 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
- 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?
- 4. Is the anchorage free of visible cracks in the concrete near the anchors?5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
Y'0ýNEI YXNEI UD N/Al Y;4 NEI UEI N/AE Yo' NE ULI N/AE YK NEI U3 N/A13*ML&11e4:7
- ~ E , 0 Q -0009 4) Rev. I1I 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
Y[ NEI UE-12 Enter the equipment class name from Appendix B: Classes of Equipment.
<C-3 >Limerick Generating Station Unit 1 MPR-3796, Revision 1"nrrP.mnnnrs.nr.P
-in "R5-19-171 C-104 Sheet 2 of 2 Equipment ID. No. 4 4 Tnr Equip. ClassL2 (02) Transformers Equipment Description 4KV-480V Transformer Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?
%No s6Me 4e 1 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?
ooveceoJ u-, Jvf r-Aly wiour4A'A 9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YX NEI UDl N/AD YjX NO UDI N/AD YX NEI U- N/AD YWND UO Other Adverse Conditions
- 11. Have you looked for and found no other seismic conditions that could Y N UD adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
N/A Evaluated b Y: Date: 00 A/C 0, Limerick Generating Station Unit 1 MPR-3796, Revision 1 C.nrrf'qnnndlPnr.-
Nn" RP-19-171 C-105 Equipment ID: 10X204 Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrP.nnndPnr.P Nnf RR-19-171 C-1 06 Equipment ID: 10X204 Limerick Generating Station Unit 1 MPR-3796, Revision 1 rCnrrP..nnndn.nr.
Nn RR-12-171 C-107 Equipment ID: 10X204 Limerick Generating Station Unit 1 C-108 MPR-3796, Revision 1 r.nrrP'-nnndPnr.P Nn
- R5-1 -171 Equipment ID: 10X204 Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrP..nnndPlnrjP Nn' RP-1 9-171 C-109 Shept 1 of 2 Status: nV N U Seismic Walkdown Checklist (SWC)Equipment ID No. 10X282 Equip. Class 1 2 (02) Transformers Equipment Description B Reactor Enclosure HVAC Transformer Location:
Bldg. *~ucto,- Floor El. 304 Room, Area Room 619 Location:
Bldg. e Floor El. 304 Room, Area Room 619 Manufacturer, Model, Etc. (optional but recommended)
Instructions for Completing Checklist This checklist may be used to document-the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.
Additional space is provided at the end of this checklist for documenting other comments.Anchorag-e
- 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
- 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?
- 4. Is the anchorage free of visible cracks in the concrete near the anchors?5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
- 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
YO N Y-VP(NEI UEI N/AD Y&( NO U'] N/AD* NEI UD N/AD YUJ NEIUE1 NIAr INEIUE1 12 Enter the equipment class name from Appendix B: Classes of Equipment.
<C-3 >)Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrP.nnndpnrr.P Nn -PR-19-171 C-110 Sheet 2 of 2 Equipment ID No. 10X282 Equip. Class12 (02) Transformers Equipment Description B Reactor Enclosure HVAC Transformer Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?
A/ Jo so-m NEI- U[3 N/AD 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YOg NE]and masonry block walls not likely to collapse onto the equipment?
M04#d4oje Av)C4 O\K'Nwcij
("101Y MourdrA UCi N/AD 9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YJ; NO U' N/AD Y)< NEI UI" Other Adverse Conditions
- 11. Have you looked for and found no other seismic conditions that could Y?6 ND UDi adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
.QVFA Evaluated bZ...........
=I!"-F Date:< C-4 >Limerick Generating.Station Unit 1 MPR-3796, Revision 1 rlnrrP~nnndrnrt Nn* RS-19-171 C-111 Equipment ID: 10X282 Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrp.nnnr1Pnr.P Nn -RR-19-171 C-112 Equipment ID: 10X282 Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrPnnndnr.P Nn -R.-19-171 C-113 Equipment ID: 10X282 Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrPqnnnrisnr.P Nn
- R5-19-171 C-114 Sheet 1 of 2 Status:Q N U Seismic Walkdown Checklist (SWC)Equipment ID No. 4 ,0 Equip. Class12 (Iz) ..,S .EquipmentDescription
,3,;b N/ ) vAC ' , ,,,- $,. ýoL Ihs,.Location:
Bldg. FloorEl. ,3L Room, Area Room 432, Mooremd%"%ft Manufacturer, Model, Etc. (optional but recommended) 0IA/1TAC ni L Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.
Additional space is provided at the end of this checklist for documenting other comments.Anchora2e 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
- 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?
- 4. Is the anchorage free of visible cracks in the concrete near the anchors?A~ ffw (,AAc-i~JS i "J Cqee'rr PAP Y U T Nar/4pFFC-T-IA' C4 5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
- 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
YCINix Y ' Nri U[r N/Al]YX NO UI] N/AD YP NEI Ul] N/AO YE] NE] U[] N/A[.Y, NEI U-I 12 Enter the equipment class name from Appendix B: Classes of Equipment.
<C-3 >, Limerick Generating Station Unit 1 MPR-3796, Revision 1 C'nrrPqnnnrHPnr-.
Nn
- RR-19-171 C-115 Sheet 2 Of 2 Equipment ID No. 10 Q10 Equip. Class2 (?,) bAtri%-' IN, farind Equipment Description rr; .t, Sto(.9'j y4C , I oY'/rA' q I.rv& j_ Ac.Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?
Y ,NDI UD N/AD CygooffD MU--#. CWH~fa.-,)
CHArIA10.l OFF tAIJ'IDI bIES14NaiTeD "ARV¢i C,.tVL.J) ti/t, 6 4)7'Xr tO CAsLASf-r AU I-"CA oJ IS o#S LY D&)e" OLY1Oe" Vqp4e, pPA1W6- cooref $jc? " PVC -Lp.S, 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YMj ND UO N/AD and masonry block walls not likely to collapse onto the equipment?
A,/1. 0 a.v, 2;(Vt4FOVV 44i 1OFCýjYcje~-DACWVvA6VFW
>4-C,-4Tf AM ,-6~ 4/kOAR) ~~s~j~cn~p~
gcf)pr ~ ;KE A MO (A 0L 9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?UD N/AD Y&NCI UI Other Adverse Conditions
- 11. Have you looked for and found no other seismic conditions that could Y _ NO UD adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
V' TALL pAtV 6 oL. TtP MtAC01; CMS. i-tf- HA / lL/qrwe Mt. io.-2f L-. t,-.o-,WCi r-'g6,vT n-o emeIeo .
Evaluated by: Date: 8, 3- ?0 :j& 1 /-3 f zt:2----6/Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrPc-nnndpnrP Nn -RR-19-171 C-116 Equipment ID: 10Y104 Limerick Generating Station Unit 1 MPR-3796, Revision 1 flnrrs-qnnndPnrP, Nn -RR-1 -171 C-117 Equipment ID: 10Y104 Limerick Generating Station Unit 1 MPR-3796, Revision 1 rfnrrpqnnndpnr'P Nn -R 171 C-118 Equipment ID: 10Y104 Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrAqnnndPnr.A Nn
- RR-12-171 C-119 Sheet 1 of 2 Status: (g N U Seismic Walkdown Checklist (SWC)Equipment ID No. 1A2D101 Equip. Class 1 2 (13) Batteries
& Racks Equipment Description 125 VDC Batte Location:
Bldg. Cynfro Floor El. 2,9 Room, Area Room 436 Structure Manufacturer, Model, Etc. (optional but recommended)
Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.
Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
JU NEI 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?
- 4. Is the anchorage free of visible cracks in the concrete near the anchors?5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
Mo 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
AIV 0 a)vilyV0-5I jr -0IfUD N/AO Y/NO Ur N/AU]UO] N/AUI YK NEI U- N/AF Yu'iNf] UF'1 2 Enter the equipment class name from Appendix B: Classes of Equipment.
Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrre~nnnr~nr,-
Nn -RR-19-171 C-120 Sheet 2 of 2 Equipment ID No. lA2D101 Equip. Class" 2 (13) Batteries.&
Racks Equipment Description 125VDC Battery Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?
- 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?
C--GOSf,g.ev.
- 9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction ev4'uations, is equipment free of potentially adverse seismic-interaction/effects?
~~ '" 14tUX4S 460 erof~ef +?'.~trhU" N/AO Y[E/ND UD N/A-Y( NO UO N/AD Y4N" UD Other Adverse Conditions
/11. Have you looked for and found no other seismic conditions that could Yd NO UI" adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary) k.,ý6, ij'e JrAu~Evaluated Date:<C-4>Limerick Generating Station Unit 1 MPR-3796, Revision 1 rlnrrPgnnnrIpnr.P Nn* RR-19-171 C-121 Equipment ID: 1A2D101 Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrP NfnnnlPnrP.Nn*
RR-19-171 C-122 Equipment ID: 1A2D1O1 Limerick Generating Station Unit 1 MPR-3796, Revision 1 fnrrPqnnnrlPnr.P Nn -Pq-1?-171 C-123 Sheet I of 2 Status: (& N U Seismic Walkdown Checklist (SWC)Mo A Equipment ID No. 114C563 Equip. Class (1@8) Control Panels & Cabinets Equipment Description Diesel Generator Enclosure HVAC Control Panel Location:
Bldg. Diesel Floor El. 217 Room, Area Room 311B" *e-" Generator Building Manufacturer, Model, Etc. (optional but recommended)
Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.
Additional space is provided at the end of this checklist for documenting other co e ts.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
- 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?
- 4. Is the anchorage free of visible cracks in the concrete near the anchors?-rig e s Iva &,v-wr~e~t~ -A cae iv .sA I~S~P LrVP 5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
- 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
YO/ND1 UQ' N/AD YZ/NI-I U" N/AD1ýY NEI UDN/WgO YD NEI U N/Au Ywl/NDo UD 1 2 Enter the equipment class name from Appendix B: Classes of Equipment.
SC-3 >Limerick Generating Station Unit 1 MPR-3796, Revision 1 Cnrrm.nnnHPnr'P Nn " R.-17-171 C-124 Sheet 2 of 2 Equipment ID No. {iC563 Equip. Class'2 (18) Control Panels & Cabinets I Equipment Description Diesel Generator Enclosure HVA C Control Panel Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?
j getfee U pog1" Lt/-Hr /.jA-go4 y V 1r 17 cA-"' I v? c terr 'TH4- )~': Fx-oft[ If f fape.8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?
9 9. o attached lines have adequate flexibility to avoid damane?ff/4cP Li(t A./e-C~10. Based on' the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YO/NJ Y[2&C: YdNEI UD N/AD UI N/Al]UC] N/AC YN N UC Other Adverse Conditions
- 11. Have you looked for and found no other seismic conditions that could Y2(NO' U-]adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
Evaluated by: Date: 7/3 /Z.1 403 1-2-< C-4 A>Limerick Generating Station Unit 1 MPR-3796, Revision 1 flnrrP.nnnr1Pnr'P Nn
- R;-19-171 C-125 Equipment ID: 1AC563 Limerick Generating Station Unit 1 MPR-3796, Revision 1 Nn -RR-19-171 C-126 Equipment ID: 1AC563 Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrp.nnndPnr-np n
- R.R-19-171 C-127 Sheet 1 of 2 Status: (, N U Seismic Walkdown Checklist (SWC)Equipment ID No. lAD106 Equip. Class" 2 (18) Control Panels & Cabinets Equipment Description 125/25OVDC Current Transducer Panel Location:
Bldg. Control Floor El. 239 Room, Area Room 435 Structure Manufacturer, Model, Etc. (optional but recommended)
Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgrnents and findings.
Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
- 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?
- 4. Is the anchorage free of visible cracks in the concrete near the anchors?5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
- 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
A/c' ~3Sd / Aýff~ 4~e fIii e t'~O"' 5 YIND(YI2N[- U[- N/A[Y&~NO UD- N/AO YEJN-l U- N/All YO NEI UD- N/At YE'NE- U" 12 Enter the equipment class name from Appendix B: Classes of Equipment.
<C-3 >Limerick Generating Station Unit 1 MPR-3796, Revision 1 rTnrrp.nnndrpnr-Nn" RR-19-171 C-128 Sheet 2 of 2 Equipment ID No. lAD 106 Equip. Class" (18) Control Panels & Cabinets Equipment Description 12,5250VDC Current Transducer Panel Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?
Yfid NO UD N/AD 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y[' NE and masonry block walls not likely to collapse onto the equipment?
-fi-Hu 6'--f-w- fpALL C&CM~IL- 101/101 IIA.j A9t6QO#Tt ArsYMOOA 4 1 o14 iweg T-f At'J v'4ILL /JOT df*L. or., Tk4e e~uifPtrýi~T
,,-, UDi N/All 40 jeI.dkwll" b, A &-V' reAjwl~ er 2).-',0. C--;s-t gRc~~adD.
6Kv.~Ef~9. Do attached lines have adequate flexibility to avoid damage? Yý NDI UD N/A[D 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YFIe/NE UO Other Adverse Conditions
- 11. Have you looked for and found no other seismic conditions that could Y[i/ND1 UOD adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
Evaluated by: Date: Limerick Generating Station Unit 1 MPR-3796, Revision 1 ('nrrP.nnndPnr.P.
Nn' RR-19-171 C-129 Equipment ID: 1AD106 Limerick Generating Station Unit 1 C-130 MPR-3796, Revision 1 (lnrrp.nnnrIi-.nrt.p Nn Equipment ID: 1AD106 Limerick Generating Station Unit 1 MPR-3796, Revision 1 (,,nrrmnnndnrnP Nn -RR-19-171 C-131 Sheet I of 2 Status:) N U Seismic Walkdown Checklist (SWC)Equipment ID No. lAD160 Equip. Classi 2 (14) Batte Chargers and Inverters Equipment Description A RPS & UPS Distribution Panel Static Inverter Location:
Bldg. Contro Floor El. 254 Room, Area Room 452 Structure Manufacturer, Model, Etc. (optional but recommended)
Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.
Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
ynI 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?
- 4. Is the anchorage free of visible cracks in the concrete near the anchors?5. Is the anchorage configuration consistent with plant documentation?
\ (Note: This question only applies if the item is one of the 50% for which an nchorage configuration verification is required.)
Ars4^6,b 'm 4a tout- CV14,n4( p fia,O C-c~wiefs Ol 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
YX NO UE N/AU Y;LNOD U1 N/A]Y)E.ND UD N/AO YE]NEI UO N/AX YIKNl] 1)0 Enter the equipment class name from Appendix B: Classes of Equipment.
<C-3 )>Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrPqnnnHPinr.P' Nn RR-17-171 C-132 Sheet 2 of 2 Equipment ID No. 1AD160 Equip. Class1 2 (14) Battery Chargers and Inverters Equipment Description A RPS & UPS Distribution Panel Static Inverter Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?
8.Are overhet~ad l equiment disriutinssemselin til4-es n igtn, X7rD UfD N/AD 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?
Do attached lines have adequate flexibility to avoid damage? W 0 UO NJAO~r'CL ~ ~ low6 M. C 11-/40f Ufi NIAO 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Sc4II t O 4ftV)1t Aswo L~0 9.~);KNEI UO O*(rS9C 'Lf h4S Other Adverse Conditions
- 11. Have you looked for and found no other seismic conditions that could '!k, N[i UOI adversdly affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
Evaluted y:-e lits Date:< C4>Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrPqnnnHPgnr.
Nn R5.-19-171 C-133 Equipment ID: 1AD160 Limerick Generating Station Unit 1 MPR-3796, Revision 1 r.nrrP.nnndPnr-.P Nn