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Category:Report
MONTHYEARML24026A2962024-01-26026 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, Owner'S Activity Report (OAR-1) for Li2R 172023-08-10010 August 2023 Owner'S 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 ML14133A0222014-05-13013 May 2014 ACE Document Received at LIM Aam May 7, 2014 ML14133A0162014-05-13013 May 2014 ACE Attachment to NRC Chairman Macfarlane Letter of 3-31-14 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 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 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 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 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 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 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 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 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 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 2024-01-26
[Table view] Category:Miscellaneous
MONTHYEARLG-23-059, Owner'S Activity Report (OAR-1) for Li2R 172023-08-10010 August 2023 Owner'S 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 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 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 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 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 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 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 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 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 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 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 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 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 ML12342A1262012-11-0606 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 8 of 13 2023-08-10
[Table view] |
Text
Sheet 1 of 2 Status:(0 N U Seismic Walkdown Checklist (SWC)Equipment ID No. 2I 205 Equip. Class" (19) Vertical Tanks or Heat Exchangers Equipment Description 2B Residual Heat Removal Heat Exchanger Location:
Bldg. Reactor Floor El. 177 Room, Area Room 174 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.Anchoraize
- 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.* eNi, Owl, #3+Q- P-6 Olo.5 R Vk 0 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
--%N-Yo NE] U[J N/A[Y ND UQ N/A[l Y% NEI UE N/AE-YX NEI UI N/AO* NfE UE-12 Enter the equipment class name from Appendix B: Classes of Equipment.
<C-3 >" Limerick Generating Station Unit 2 MPR-3801, Revision I flnrrqnnnd(nrt-.
Nn
- RR-19-171 C-225 Sheet 2 of 2 Equipment ID No. 2BE205 Equip. Class 1 2 (19) Vertical Tanks or Heat Exchangers Equipment Description 2B Residual Heat Removal Heat Exchanger 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?, A o a r eo&J 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?YD( ND UD N/AD YN( ND UD N/AD YV ND UD N/AD 1)( ND UD Other Adverse Conditions
- 11. Have you looked for and found no other seismic conditions that could NO NiUD adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
Evaluated by Date: 4 Limerick Generating Station Unit 2 MPR-3801, Revision 1 rnrrPnnndP~nr.P Nn -PS-19-171 C-226 Equipment ID: 2BE205 I Limerick Generating Station Unit 2 MPR-3801, Revision 1 rnrrPnnnH1nr.P Nn -RR-19-171 C-227 Equipment ID: 2BE205 Limerick Generating Station Unit 2 C-228 MPR-3801, Revision 1 rnrrPqnnndpnr.nn Nn 'RR-19-171 Equipment ID: 2BE205 Limerick Generating Station Unit 2 MPR-3801, Revision 1 r.nrrP'qnnndPnrP'.
Nn -RIR-1-171 C-229 Equipment ID: 2BE205 Limerick Generating Station Unit 2 MPR-3801, Revision 1 rnrr.-nnnrPnr Nn R.R-19-171 C-230 Equipment ID: 2BE205 Limerick Generating Station Unit 2 MPR-3801, Revision 1 Nn -RR-19-171 C-231 Equipment ID: 2BE205 Limerick Generating Station Unit 2 MPR-3801, Revision 1 rlnrr-.qnnndPnnp Nn* RR-19-171 C-232 Sheet i of 2 Status:O N U Seismic Walkdown Checklist (SWC)Equipment ID No. 2BS252%1N Equip. Class" (19) Vertical Tanks or Heat Exchangers Equipment Description PCIG/ADS Nitrogen Bottles Location:
Bldg. Reactor Floor El. 217 Room, Area Room 370E 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.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?
YXNEI X4 NEI ULI N/A[lUDl N/AI" YVNEI UE- N/AEl Y INEI UEJ N/ADl YX NEI UD 12 Enter the equipment class name from Appendix B: Classes of Equipment.>Limerick Generating Station Unit 2 MPR-3801, Revision 1 rnrrPqnnndPnrA.
Nn ' RR-19-171 C-233 Sheet 2 of 2 Equipment ID No.
Equip. Class'2 (19) Vertical Tanks or Heat Exchangers Equipment Description PCIG/ADS Nitrogen Bottles Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?
1 J 0 C2 4 ,tU k Y)NEI UD N/AD 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YX NE UEJ N/AD and masonry block walls not likel to collapse onto the equipment?
- 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?Y(NO UEJ N/AD YX ND Uo Other Adverse Conditions
- 11. Have you looked for and found no other seismic conditions that could YK ND UD adversely affect the safety functions of the equipment?.R ~u~ 6~bX A# _6 6)~h roIck I -- ur Comments (Additional pages may be added as necessary)
IQ/A 1 Evaluated by t°el-Date: /I ( ý )< C-4 >Limerick Generating Station Unit 2 MPR-3801, Revision 1 r.nrrP NnnndPn n N Ro 171 C-234 Equipment ID: 2BS252 Limerick Generating Station Unit 2 MPR-3801, Revision 1 rnrrPqnnnriPnr.P Nn " R5-19-171 C-235 Equipment ID: 2BS252 Limerick Generating Station Unit 2 MPR-3801, Revision 1 rlnrrmnnndpnr.P Nn ' RR-12-171 C-236 Equipment ID: 2BS252 Limerick Generating Station Unit 2 MPR-3801, Revision 1 rnrrqnnnrlPnc Nln* RR-19-171 C-237 Equipment ID: 2BS252 Limerick Generating Station Unit 2 MPR-3801, Revision 1 rnrrP'qnnnHlAnrn.
Nn -R5-19-171 C-238-j Sheet 1 of 2 Status:@ N U Seismic Walkdown Checklist (SWC)Equipment ID No. 2BS921 Equip. Class 2 (18) Control Panels & Cabinets Equipment Description Main Steam Relief Valve Position Transmitter Pre-Amp Location:
Bldg. Reactor Floor El. 253 Room, Area Room 475W 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.Anchoraae 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?
YDNDI UD" N/AD]Yb NDI U[D] N/AD_]YX NDI UD N/AD YO NDI UD- N/AX YX NEI U[D]12 Enter the equipment class name from Appendix B: Classes of Equipment.
<C-3 >Limerick Generating Station Unit 2 MPR-3801, Revision 1 rnrrP.qnnnHPlnrP Nn -R.9-1 7-171 C-239 Sheet 2 of 2 Equipment ID No. 2BS921 Equip. Class" 2 (18) Control Panels & Cabinets Equipment Description Main Steam Relief Valve Position Transmitter Pre-Amp Interaction Effects 7. Are soft targets free fron impact by nearby equipment or structures?, Ala 'i A 4-4vle 5 Yt NO UD N/AD 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YX NO UD N/AQ and masonry block walls not likely to collapse onto the eauipmentd jwell Lov ýor r -a~l .,u,:.NVirl 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?YI( NE UD N/AD Yt NE UD Other Adverse Conditions
- 11. Have you looked for and found no other seismic conditions that could Y14 NO UO adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
Evaluated by: a.iqL -Date:< C-4 A>Limerick Generating Station Unit 2 MPR-3801, Revision 1 n.orrPnnndPn-nP Nn
- RR-1 9-171 C-240 Equipment ID: 2BS921 Limerick Generating Station Unit 2 MPR-3801, Revision 1 C'nrrP.nnndPnnrP Nn" RR-19-171 C-241 Equipment ID: 2BS921 Limerick Generating Station Unit 2 MPR-3801, Revision 1 CnrrPnnnrlpnrA Nn RR-17-171 C-242 Sheet 1 of 2 Status:& N U Seismic Walkdown Checklist (SWC)Equipment ID No. 2BT528 Equip. Class" (19) Vertical Tanks or Heat Exchangers Equipment Description Diesel Generator Day Tank Location:
Bldg. Genera Floor El. 217 Room, Area Room 316fJi Generatoru 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 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?x-,NEI YP NI Ur- N/Asl YJI"C UEI N/ACU- N/AC JNEI Ur- N/AI-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 anchgrage confiuration vei is required.)
Y6C UE 9MAO q/2/12-z 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
1 Enter the equipment class name from Appendix B: Classes of Equipment.
<C-3 >Limerick Generating Station Unit 2 MPR-3801, Revision 1 CrnrrP.qnnnriPnr.P.Nn R.R-19-171 C-243 Sheet 2 of 2 Equipment ID No. 2BT528 Equip. Class 1 2 (19) Vertical Tanks or Heat Exchangers Equipment Description Diesel Generator Day Tank Interaction Effects 7. Are soft targets free from impact by nearly equipnent or structures?
- 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?
, 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?6cei ty; Or'(6'YANND UD N/AD)XN-1 UD N/ADl Y,(ND- UDI N/ADl YgNI! UD Other Adverse Conditions
- 11. Have you looked for and found no other seismic conditions that could Y4 NDI U[I adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
AI an O-11A /Evaluated by: //-I /.L-Date: At d-1.- 7 Limerick Generating Station Unit 2 MPR-3801, Revision 1 rlnrrPqnnndPnrn.
Nn- RR-19-171 C-244 Equipment ID: 2BT528 Limerick Generating Station Unit 2 MPR-3801, Revision 1 rnrrPmnnndInrP.
Nn ' RR-19-171 C-245 Sheet 1 of 2 Status: (9 N U Seismic Walkdown Checklist (SWC)Equipment ID No. 2BV208 Equip. Class 1 2 (08) Fans & Air Handlers Equipment Description RCOC Pump & Turbine Room Cooler Location:
Bldg. Reactor Floor El. 177 Room, Area Room 179 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.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 f visible cracks in the concrete near the anchors?f40Uq c6 ZZ 0 54* 'ro 54v6 onc.M J6 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 NEIUD N/AD YWjNO UD N/AD YbiNO UO cmck(4fýN/AD YJ, ND UD N/AD YJZ ND UD 12 Enter the equipment class name from Appendix B: Classes of Equipment.
<C-3 >Limerick Generating Station Unit 2 MPR-3801, Revision 1 rTnrrPAnnnrHp.nrP Nn -RS-19-171 C-246 Sheet 2 of 2 Equipment ID No. 2BV208 eEquip. Class" (08) Fans & Air Handlers Equipment Description RCIC Pump & Turbine Room Cooler 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?
- 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 UD- N/ADlNEI UE- N/AD'YX N[3 UDI N/ADl YX NEI UED Other Adverse Conditions
- 11. Have you looked for and found no other seismic conditions that could N% NEI UO adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
[VIA (6rtw_ or:ýýM.Evaluated by 6'K?2~-~ t Date: r I/1< C-4 >Limerick Generating Station Unit 2 MPR-3801, Revision 1 rnrrmnnnrdn.nrP Nn* R.R-19-171 C-247 Equipment ID: 2BV208 B Limerick Generating Station Unit 2 MPR-3801, Revision 1 Nn
- RR-19-171 C-248 Equipment ID: 2BV208 I Limerick Generating Station Unit 2 MPR-3801, Revision 1 (lnrrAnrnndnr-Nn RR-1 9-171 C-249 Sheet 1 of 2 Status: (P N U Seismic Walkdown Checklist (SWC)Equipment ID No. -2A-W08- Equip. Class 1 2 (08) Fans & Air Handlers"P .rt~nmt-nf i'-qri ;nf 444."PLimn A Tirhimo P fnh, Location:
Bldg. Reactor Floor El. 177 Room, Area Room-19* 8 ) 0 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.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
YX ND 2. Is the anchorage free of bent, broken, missing or loose hardware?
YP( ND UD N/AD 3. Is the anchorage free of corrosion that is more than mild surface YI ND UD N/AD oxidation?
- 4. Is the anchorage free of visible cracks in the concrete near the anchors? Y) ND UD N/AD 5. Is the anchorage configuration consistent with plant documentation?
YN ND UD N/AD (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 Y;9 ND UD potentially adverse seismic conditions?
12Enter the equipment class name from Appendix B: Classes of Equipment.
<C-3 >Limerick Generating Station Unit 2 MPR-3801, Revision 1 CnrrP.-nnndPnrýp Nn -RR-19-171 C-250 Sheet 2 of 2 Equipment ID No. 6 I3V Equip. Class'2 (08) Fans & Air Handlers H P61 Equipment Description -Rk&Pump & Turbine Room Cooler Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?
Nlo --, *4 4F,3 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?
NA/o o\Aiads 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?Y4 NO UD-I N/AD Y4ND UD N/AD Y& ND UD N/AD YKNE UD Other Adverse Conditions
- 11. Have you looked for and found no other seismic conditions that could Yk( ND UQ adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
N/A Evaluated by: QfwrJ-~T~ae~Date: V2 L-n<C-4>Limerick Generating Station Unit 2 MPR-3801, Revision 1 r.nrrm¢nnndPnr-.p Nn -RA-19-171 C-251 Equipment ID: 2BV209 Limerick Generating Station Unit 2 MPR-3801, Revision 1 C.nrrP.nnndPnrnA Nn* R.S-12-171 C-252 Equipment ID: 2BV209 Limerick Generating Station Unit 2 MPR-3801, Revision 1 r(nrr~mnnnhPnr.P Nn* R5R-19-171 C-253 Equipment ID: 2BV209 Limerick Generating Station Unit 2 MPR-3801, Revision 1 Nn" R5R-19-171 C-254 Equipment ID: 2BV209 Limerick Generating Station Unit 2 MPR-3801, Revision 1 r.nrr.nnndP~n-.
Nn
- RR-19-171 C-255 Equipment ID: 2BV209 Limerick Generating Station Unit 2 MPR-3801, Revision 1 rnrrpiqnnndpnr,.
Nn -RR-12-171 C-256 Sheet 1 of 2 Status:6 N U Seismic Walkdown Checklist (SWC)Equipment ID No. 2CD101 Equip. Class 1 2 (13) Batteries
& Racks Equipment Description 125 VDC Batteg Location:
Bldg. Control Floor El. 217 Room, Area Room 361 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.Anchoraie 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 au anchorage configuration veriication is required.)M
- 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
NE UO N/AE 2CNO gNEI U[3 N/A[UD N/A0 UD N/A[XNO UD 12 Enter the equipment class name from Appendix B: Classes of Equipment.
<C-3 )" Limerick Generating Station Unit 2 MPR-3801, Revision 1 Nn* RR-19-171 C-257 Sheet 2 of 2 Equipment ID No. 2CDl01 Equip. Class 1 2 (13) Batteries
& Racks Equipment Description 125 VDC Battery Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?
YA NE UD N/AO 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YXd NO UD N/AO d masonry bock walls not likely to collapse onto the equipment?
p '? L4" #I 49V V2CYIK--UE
'Y t5ksý9. Do attached lines h ve gdequate flebiit to avoid damage? " Y ND UO N/A rO C--p.Mto'i/i 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y)6.No UO Other Adverse Conditions
- 11. Have you looked for and found no other seismic conditions that could YA NO UD adversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
Date:< C-4 >Limerick Generating Station Unit 2 MPR-3801, Revision 1 rnrrPnnndPnr.P Nn
- PR-19-171 C-258 Equipment ID: 2CD101 Limerick Generating Station Unit 2 MPR-3801, Revision 1 rlnrrPqnnndPnrP Nn" RR-19-171 C-259 Equipment ID: 2CD101 Limerick Generating Station Unit 2 MPR-3801, Revision 1 Mn