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Category:Report
MONTHYEARML23325A2022024-01-16016 January 2024 CFR Part 52 Construction Lessons-Learned Report NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error ML24004A2192024-01-0808 January 2024 Construction Reactor Oversight Process Performance Metric Report for Calendar Year 2023 ND-23-0025, Compliance with Order EA-12-0492023-08-21021 August 2023 Compliance with Order EA-12-049 ML22348A0932023-07-28028 July 2023 Finding That the Acceptance Criteria in the Combined License Are Met ML22348A0882023-07-25025 July 2023 VEGP Unit 4 - 103g - Basis Document ML23184A0472023-07-0303 July 2023 Dashboard Report 7-3-2023 ML23156A1882023-06-0505 June 2023 Construction Reactor Oversight Process Resources Report June 5, 2023 ML23121A0392023-05-0101 May 2023 Dashboard Report 5-1-2023 ML23003A0412023-01-0303 January 2023 Construction Reactor Oversight Process Resources Report January 3, 2023 ND-22-0817, Enclosures 1 and 2: Proposed Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds and Alternative for Use of Code Case 648-2 for Inservice Inspection2022-11-0404 November 2022 Enclosures 1 and 2: Proposed Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds and Alternative for Use of Code Case 648-2 for Inservice Inspection ND-22-0831, (Vegp), Units 3 and 4, Comments on AP1000 Standard Technical Specifications (STS) Draft NUREG-2194, Revision 12022-10-31031 October 2022 (Vegp), Units 3 and 4, Comments on AP1000 Standard Technical Specifications (STS) Draft NUREG-2194, Revision 1 ML22278A0382022-10-0505 October 2022 Dashboard Report 10-5-2022 ML22215A0962022-08-0303 August 2022 Construction Reactor Oversight Process Resources Report August 3, 2022 ML22214A0072022-08-0101 August 2022 Archives ML20290A2762022-08-0101 August 2022 10CFR52.103(g) Basis Document NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 ML22179A1462022-06-15015 June 2022 Tier 1, Revision 10, Updated Through 04/22/2022 ML22159A1712022-06-0808 June 2022 Construction Reactor Oversight Process Resources Report June 8, 2022 ML22131A0502022-05-11011 May 2022 Construction Reactor Oversight Process Resources Report May 11, 2022 ML22089A0412022-03-30030 March 2022 Construction Reactor Oversight Process Resources Report March 30 2022 ND-22-0003, Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report2022-01-0606 January 2022 Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report ND-21-1003, Request for Exemption: Applicability of 10 CFR 26.3. Scope, Until Initial Fuel Load - Supplement2021-11-12012 November 2021 Request for Exemption: Applicability of 10 CFR 26.3. Scope, Until Initial Fuel Load - Supplement ND-21-0991, Exemption Request: Applicability of 10 CFR 26.3, Scope, Until Initial Fuel Load2021-11-0505 November 2021 Exemption Request: Applicability of 10 CFR 26.3, Scope, Until Initial Fuel Load ML21280A3042021-10-0707 October 2021 Q 2020 Performance Summary ML21280A3052021-10-0707 October 2021 Q/2020 Performance Summary ML21277A0762021-10-0404 October 2021 Vog 4 Dashboard 10-4-2021 ND-21-0848, Enclosure - Unit 4 Operator Candidates Requesting Credit for Unit 3 Written Examination and Operating Test (Revised)2021-10-0101 October 2021 Enclosure - Unit 4 Operator Candidates Requesting Credit for Unit 3 Written Examination and Operating Test (Revised) IR 05000424/20210052021-08-25025 August 2021 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 (Report 05000424/2021005 and 05000425/2021005) ND-21-0603, Electrical Construction and Measuring & Test Equipment Control2021-06-25025 June 2021 Electrical Construction and Measuring & Test Equipment Control ML21179A0972021-06-15015 June 2021 to Tier 1 ML21132A0482021-05-12012 May 2021 Construction Reactor Oversight Process Resources Report May 2021 ML21118A1162021-04-28028 April 2021 Emergency Response Data System (ERDS) Data Point Library for Vogtle Unit 3 ND-21-0342, Emergency Response Data System (ERDS) Data Point Library for Vogtie Unit 42021-04-28028 April 2021 Emergency Response Data System (ERDS) Data Point Library for Vogtie Unit 4 ML21090A2092021-03-31031 March 2021 Construction Reactor Oversight Process Resources Report March 2021 ML21040A1672021-02-0909 February 2021 (Vegp), Units 3 and 4, Revision to Westinghouse Non-Proprietary Technical Description of the Flaw Tolerance Evaluation Conducted on the Subject Weldolet Branch Connections ML20358A1822020-12-31031 December 2020 LTR-SDA-20-096-NP, Revision 1, Flaw Tolerance Evaluation to Assess Lack of Inspection Coverage of AP1000 14 X 4 Stainless Steel Weldolets to Pipe Welds ML20343A0672020-12-0202 December 2020 Dashboard Report 12-2-2020 ML20314A0492020-11-0909 November 2020 Construction Reactor Oversight Process Resources November 2020 ND-20-1220, Report of Changes Incorporated Into Revision 6 to the Security Plan, Training and Qualification Plan, and Safeguards Contingencv Plan2020-10-21021 October 2020 Report of Changes Incorporated Into Revision 6 to the Security Plan, Training and Qualification Plan, and Safeguards Contingencv Plan ML20287A1862020-10-13013 October 2020 Construction Reactor Oversight Process Resources October 2020 ML20274A2582020-09-10010 September 2020 Wp on Uswc for AP1000_Revised, Reactor Oversight Process Whitepaper - Modification of the Description of Unplanned Scrams with Complications Performance Indicator to Reflect AP1000 Design ML20191A3832020-08-14014 August 2020 Transition to Reactor Oversight Process for Vogtle Electric Generating Plant, Units 3 and 4 ND-20-0907, Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1)2020-07-28028 July 2020 Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1) ND-20-0561, Submittal of Turbine Maintenance and Inspection Program in Accordance with Updated Final Safety Analysis Report2020-07-10010 July 2020 Submittal of Turbine Maintenance and Inspection Program in Accordance with Updated Final Safety Analysis Report ML20189A4292020-07-0707 July 2020 Construction Reactor Oversight Process Resources July 2020 ML20136A4562020-04-30030 April 2020 Updated Flex Plan Nuclear Regulatory Commission Order EA-12-049 Strategies for Beyond Design Basis External Events NL-19-0832, EPRI Technical Report 3002014590, Technical Bases for Inspection Requirements for PWR Steam Generator Feedwater and Main Steam Nozzle-to-Shell Welds and Nozzle Inside Radius Sections.2019-12-31031 December 2019 EPRI Technical Report 3002014590, Technical Bases for Inspection Requirements for PWR Steam Generator Feedwater and Main Steam Nozzle-to-Shell Welds and Nozzle Inside Radius Sections. ML19284B3722019-11-15015 November 2019 Attachment - VEGP U3 Amendment 166 (LAR-19-008) NL-19-0674, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-09-30030 September 2019 Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 2024-01-08
[Table view] Category:Technical
MONTHYEARML23325A2022024-01-16016 January 2024 CFR Part 52 Construction Lessons-Learned Report ML24004A2192024-01-0808 January 2024 Construction Reactor Oversight Process Performance Metric Report for Calendar Year 2023 ND-23-0025, Compliance with Order EA-12-0492023-08-21021 August 2023 Compliance with Order EA-12-049 ML22348A0882023-07-25025 July 2023 VEGP Unit 4 - 103g - Basis Document ML23156A1882023-06-0505 June 2023 Construction Reactor Oversight Process Resources Report June 5, 2023 ML23121A0392023-05-0101 May 2023 Dashboard Report 5-1-2023 ML23003A0412023-01-0303 January 2023 Construction Reactor Oversight Process Resources Report January 3, 2023 ND-22-0817, Enclosures 1 and 2: Proposed Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds and Alternative for Use of Code Case 648-2 for Inservice Inspection2022-11-0404 November 2022 Enclosures 1 and 2: Proposed Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds and Alternative for Use of Code Case 648-2 for Inservice Inspection ML22278A0382022-10-0505 October 2022 Dashboard Report 10-5-2022 ML20290A2762022-08-0101 August 2022 10CFR52.103(g) Basis Document NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 ML22179A1462022-06-15015 June 2022 Tier 1, Revision 10, Updated Through 04/22/2022 ML22159A1712022-06-0808 June 2022 Construction Reactor Oversight Process Resources Report June 8, 2022 ML22089A0412022-03-30030 March 2022 Construction Reactor Oversight Process Resources Report March 30 2022 ND-22-0003, Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report2022-01-0606 January 2022 Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report ND-21-0848, Enclosure - Unit 4 Operator Candidates Requesting Credit for Unit 3 Written Examination and Operating Test (Revised)2021-10-0101 October 2021 Enclosure - Unit 4 Operator Candidates Requesting Credit for Unit 3 Written Examination and Operating Test (Revised) ML21179A0972021-06-15015 June 2021 to Tier 1 ML21132A0482021-05-12012 May 2021 Construction Reactor Oversight Process Resources Report May 2021 ND-21-0342, Emergency Response Data System (ERDS) Data Point Library for Vogtie Unit 42021-04-28028 April 2021 Emergency Response Data System (ERDS) Data Point Library for Vogtie Unit 4 ML21118A1162021-04-28028 April 2021 Emergency Response Data System (ERDS) Data Point Library for Vogtle Unit 3 ML21090A2092021-03-31031 March 2021 Construction Reactor Oversight Process Resources Report March 2021 ML21040A1672021-02-0909 February 2021 (Vegp), Units 3 and 4, Revision to Westinghouse Non-Proprietary Technical Description of the Flaw Tolerance Evaluation Conducted on the Subject Weldolet Branch Connections ML20358A1822020-12-31031 December 2020 LTR-SDA-20-096-NP, Revision 1, Flaw Tolerance Evaluation to Assess Lack of Inspection Coverage of AP1000 14 X 4 Stainless Steel Weldolets to Pipe Welds ND-20-1220, Report of Changes Incorporated Into Revision 6 to the Security Plan, Training and Qualification Plan, and Safeguards Contingencv Plan2020-10-21021 October 2020 Report of Changes Incorporated Into Revision 6 to the Security Plan, Training and Qualification Plan, and Safeguards Contingencv Plan ML20274A2582020-09-10010 September 2020 Wp on Uswc for AP1000_Revised, Reactor Oversight Process Whitepaper - Modification of the Description of Unplanned Scrams with Complications Performance Indicator to Reflect AP1000 Design ND-20-0561, Submittal of Turbine Maintenance and Inspection Program in Accordance with Updated Final Safety Analysis Report2020-07-10010 July 2020 Submittal of Turbine Maintenance and Inspection Program in Accordance with Updated Final Safety Analysis Report ML20189A4292020-07-0707 July 2020 Construction Reactor Oversight Process Resources July 2020 ML20136A4562020-04-30030 April 2020 Updated Flex Plan Nuclear Regulatory Commission Order EA-12-049 Strategies for Beyond Design Basis External Events NL-19-0832, EPRI Technical Report 3002014590, Technical Bases for Inspection Requirements for PWR Steam Generator Feedwater and Main Steam Nozzle-to-Shell Welds and Nozzle Inside Radius Sections.2019-12-31031 December 2019 EPRI Technical Report 3002014590, Technical Bases for Inspection Requirements for PWR Steam Generator Feedwater and Main Steam Nozzle-to-Shell Welds and Nozzle Inside Radius Sections. NL-19-0674, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-09-30030 September 2019 Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 ND-19-0356, Pressurized Thermal Shock (PTS) Evaluation2019-04-10010 April 2019 Pressurized Thermal Shock (PTS) Evaluation ND-19-0665, (VEGP) Units 3 and 4 - WCAP-15927-NP, Design Process for AP1000 Common Q Safety Systems, Revision 7 (Public Version)2019-03-21021 March 2019 (VEGP) Units 3 and 4 - WCAP-15927-NP, Design Process for AP1000 Common Q Safety Systems, Revision 7 (Public Version) ML19038A4632019-02-0707 February 2019 Construction Reactor Oversight Process Resources ML18275A0402018-10-31031 October 2018 Technical Evaluation Report: Use of BADGER and Narwhal to Compute Strainer Failure Probability - Vogtle Units 1 and 2 Nuclear Power Plant NL-18-0684, Fukushima Near-Term Task Force Recommendation 2.1: Seismic Supplemental Information Regarding NEI 12-06. Appendix H. Revision 4. H.4.5 Path 5 Mitigating Strategies Assessment (MSA) Report2018-06-25025 June 2018 Fukushima Near-Term Task Force Recommendation 2.1: Seismic Supplemental Information Regarding NEI 12-06. Appendix H. Revision 4. H.4.5 Path 5 Mitigating Strategies Assessment (MSA) Report NL-14-0639, Revision 5 Pressure and Temperature Limits Report and Unit 2 Revision 5 Pressure and Temperature Limits Report2014-04-22022 April 2014 Revision 5 Pressure and Temperature Limits Report and Unit 2 Revision 5 Pressure and Temperature Limits Report NL-14-0344, Seismic Hazard and Screening Report for CEUS Sites2014-03-31031 March 2014 Seismic Hazard and Screening Report for CEUS Sites ML14043A4762014-02-24024 February 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 ML14006A2012014-01-0303 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Vogtle Electric Generating Plant, Units 1 and 2, TAC Nos.: MF0714 and MF0715 ML13211A2622013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 7 of 14 NL-13-1236, SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 14 of 142013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 14 of 14 NL-13-1236, SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 13 of 142013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 13 of 14 NL-13-1236, SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 11 of 142013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 11 of 14 NL-13-1236, SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 12 of 142013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 12 of 14 NL-13-1236, SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 10 of 142013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 10 of 14 NL-13-1236, SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 9 of 142013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 9 of 14 ML13211A2432013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 9 of 14 NL-13-1236, SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 6 of 142013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 6 of 14 ML13211A2602013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 5 of 14 ML13211A2592013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 4 of 14 2024-01-08
[Table view] |
Text
NO. SNCVO61-RPT-01, VERSION 1.0 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS Sheet 1 of 2 Status:& N U Seismic Walkdown Checklist (SWC)Equipment ID No. /-/6o106-
.--4$'/ Equip. Class','Equipment Description .A,4 te2. 6'W44 4 Pr""/ 7- Lersvwfe_(P e m," , .A IT Location:
Bldg. dA2A'r-/eo4 Floor El. 2'90 Room, Area i -" -z~c Manufacturer, Model, Etc. (optional but recommended) instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings.
Additional space is provided at the end of this checklist for documenting other comments.Anchorag 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?
YO ND9 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?
- 4. Is the anchorage free of visible cracks in the concrete near the anchors?5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)
//~o 7- l 5-001 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?
YRJ NO U- N/A-Y03 NO UO N/A-YVJ NO U- N/AD YO NEI U" N/AX YX NO U-,2 Enter the equipment class name from Appendix B: Classes of Equipment.
<CC-3 >PAGE 161 of 668 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSION 1.0 Shee(t2 of02 Seismic Walkdown Checklist (SWC)Eq-iuipnent ID No. /-/$o5- Cý AS! Equip. Class1 /i'2 ,rdA1iV_/$
4OL Equipment.Description ?v/ .rt~',-yA1,c 4~fN&7 Interaction Effects 1. Are soft targets free from impact by nearby equipment oristructures?
- 8. Are overheade.quipment, distributitfiý tems, jeiling tiles and.lighting, and masýown' blo6ck wallsnot likelyto collapse ontoihe equipment?
,9. Do attached lines have adequate flexibility to avoid damage?,0.ý BaS,3 d on 4,-the above.9eisnmicihteraction eValuations, is equipment free of potentially adver*sseismic*
interaction.effects?
YN ND DUE] N/AQ YXNQ UQ. N/ADI Y,ý NI [I D[ N/AD Y% NEI UE.Other Adverse Conditions 1,1. Have you~looked for and found no other seismicconditions that coild YW N[D UD adversely affect'the"afety functioni o f the equipmenf
.....?'Comme ts (Additional pages may be added as necessary)
Evaluated by: &Zb A/k77 14,1oto4p4R$kY I Ifabit~J jIJ Date: .-.< C->.PAGE 162 of 668
- ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSIONOO PAGE 163 of 668 IACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO, SNCV061-RPT-01, VERSIO#.0 PAGE 164 of 668 I 9 ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSION .0 PAGE 165 of 668 ACHMENT 3: SEISMIC WALKDOVWN CHECKLISTS NO. SNCV061-RPT-01, VERSIANO PAGE 166 of 668
- -ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSIONOO PAGE 167 of 668
- ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSI 0 I PAGE 168 of 668 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSION 1.0 Sh4eet of 2'stats NU.Seismic WalkdOwn Checklist (SWC)EquipmentlDNo.
-oS 5-Ag .l Equip. Class'1 2 zo Equipment Description I. "r .-afo MP ~rL Z CAM Location:
Bldg. Floor El. Room, Area Manufacturer,, Model, Etc- (optional but:recommended-Instructions for Compl[ting Checklist This checklist may be used to document the results0ofthe Seismic Walkdown of anifem.of equipment on the SWEL. The sjatebeeow each oifthe foll6wing:questi6ns may be usdedto record the;results 6fjudgmentf:and findings.
Additional space :is provided at the end of this checklist for documenting other comments.Anchorte0 SEL te ri uei 1. -Is the anchorage configurationl verification required (i.re~,is the item 'one YEI NE:]of the 50% of S\VEL items r~cjirifig such verification)?
- 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is t~he anchorage free of corrosion that is more. than mild surface oxidation?
- 4. Is the anchorage free of visiblecracks in the concrete near the'aich~fs?
- 5. Is the anchorage configuration consistent with plant documentation?(Notte: This question only applie§s ifthe item is one of the .50% for which an anchorage configuration verification is required.)
- 6. Based on the above anchorage evaluati6ns, is the anchorage free of potentially adverse, seismic conditions?
YE-I NEI UE-] N/AF Y] NEI UJE] N/AD]YE] NE], UE]ý N/AE]'Yr-,NE] UE] N/AE]YE] NE] .UE P? Enter the equipment class name from Appendix 13I: Classes of Eqipmet< C-3 >PAGE 169 of 668 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSION 1.0 Sheet 2 6of2 Seismic Walkdown Checklist (SWC)Equipment ll).No. H-t6 5-C-AS , Equip. .OiasS'zc'JEquipne~nt Description zil4r Cc-&T ). ~ 2 Interaction Effects 7. Are soft targets free from impact by nearby equipfnent or structures?
8.- Are overhead'equipment, distribution~systems, ceiling, tiles andlighting,"7and .nason bjoc walls no~t likely to collapse onto the'equipment?
- 9. Do attached lines have adequate:f6exibility to avoid damaige?10. Based on the above seismic interaction evaluations, is equipment free ofpotenti.lly advei~se, seismic.iinteraction effects?YlENEI N UE N/AE1, YEI NE0 EY N/AEn YEINE UEl N/AE YEI NE UE, Oiher Adverse Conditions I1.- Ilava you looked for and found no other seismic conditions that could N%,NE U-]adversely affect the safety functions ofthe equipment?
~~N'r.twrrit4AI ov, -T~ITR~~C.1?~4~
Vrots c.Astv't-WAS vfOlMw 0:~~CKI Z tS&ALC. v o~44~t~ ~~o c~.C ~4~t0 atmv~I pV'C.A ~0 C~ ~ ~ ~ ~JANYE~ ' AV"C AV 3Vet I~C VMV.4Q~~Av- I -5Cktý.ýwt A 1K'v'~Comments (Additional pages may be a.dded as-necessary)
Evaluated by: ~ $Date.:. !,/1<C;-4 PAGE 170 of 668 ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERS1000 PAGE 171 of 668 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSION 1.0 PAGE 172 of 668 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSION 1.0 Sheet 1 of StatupU& IN U Seismic Walkdown Checklist (SWC)Eqluipment ID.No. .1 ; a -013 Eqjuip. .Class.1"2-0.Equipetesrpin X _____Location:
Bldg. .Floor El. * -Room, Area. -.ModeL Etc. (optional but recommended) 4- A)Instructions for, Completing Checklist this checklist may be.used to document the rfesuIts offthe SeismiC. Whlkdown of an itemofequipment on the SWEL. The space below 'each ofthe following questions may be used to record the results of juidgmcnts and findings.
Additional space is provided!
at the end of this checklistfdr othef, cdmihents.
Anchorage:. Is the arithorage co .iguriatioil verification required (i.e., ig:#the item one of the 50% of SWEL items reqMiring suchlverif~cation)?
YJNm 2- Is the atnchOrage free of bent, brkern, miissing or loose hardware?3. Is fre cQfcorrosion that is moretliari i ild surface oxidatioin?
- 4. Is the anchorage free of v9sibsie-cracksin'the concrete near the anchors?, 5. 1.s.the anchorage conifiguration' consistchtvwith plant d6ctidifitdtion?(Nbte'-This question only, applies if the item is one of the. 50%.forýwhich verificfion, is-requiried.), 6. Based on the above anchorage evaluations, is the anchorage ftfeof pbtentiqll adverse seismic .Conditions'?
Ye~'NEJ UEJ N/Afl YeJNQI UE1 N/AEI Y9 INQ UEJ1 N/A.[]Y[!J/ND UfJ N/-AE1 1 NEI LI'~Efter thee 11. mn ssn Me rmAppendix B: Chuses of ~quifpment.
PAGE 173 of 668 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSION 1.0 Sheet 2 6f-2: Selsmic:Walkdown Checklist (SWC)EquiprnentfD No. Arquip. Class r'3/4'~ i~'ik I 7~A!R Eqtipmenri; Description Interaction Fffects 7' Are soft targets free from impact by nearby equipmenrt or structures?
- 8. Are overhleidd equipment, distributidn syst.¢-es, Ceoiing tiles and lIghting, andmasonry block walls not likely týo collapse doito: the equipment?
- 9. Do-attached linies have adequate flexibilitV to avoid damage?YflNEI U0 N/AO Y.VNIE uC N/ACI Y5]'NC UC1 N/AC1 10. Based orniheabove seismic ,interaction evalua!tions, isequipmentfiee Yf',Nc UC1.of p6tentiail lyadverse seismic ,Other Adverse Conditions 1i1. Have you.:1oked for findfoundno othcr seismic conditions that i6uld Y[Y N'C 'UC"adyeqrsely affect the safety functions of the equipmefit?
Comfinent.f (Additiobga pages: may be added as necessary)
'Evaluated by: 9'Thý01: ;).C-4,:>PAGE 174 of 668 4TACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSIONR I PAGE 175 of 668 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSION 1.0 PAGE 176 of 668 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSION 1.0 Sheet I of 2 Stfatus:O N U Seismic Walkdown Checklist (SWC)1 Equipment ID No. 1- 1 c S5- Equip. Class'2 Equipment Description Srt4-r_:ow~
VAj&t~ Location:-
Bldg. c.6tT-0.o%-
Floor El. _ Room, Area A is 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 ofjudgments aid findings.
Additional space is provided at'the end of this checklist for documenting other cormnents.
- 1. Is the anchorage configuration verification requ~ired (i.e;, is the item one of the 50% of SWEL items requiring such verification)?'
YO NO.Is the anchorage free of bent, brqken, missing odrloose hardware?3:.,Is.the anchorage free of corrosion that is more than mild sudface oxidation?
- 4. Is the anchorage free of visible cracks in the concrete near ihe anichors?5. Is the aifi6hrage cofig"uratio'n, consistenit'with plant documentution?(Note; This question only applies if the item is one of the 50% for which, an anclorage configquation verificatibn is rtequired.,)
6., Based on the above anchorage evaluations, is the anchorage free of, potentially adverse seismic¢conditions?-
YO] NC1 UC N/AC YE] NO UC11 N./AC YE] NC Ufl N/AC YC: NEI UC1 N/AC YEI NEI UE IZ Enter the equipment class name freni Appendix B: Classes ofEquipmen&,.
< C >PAGE 177 of 668 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSION 1.0 Sheet 2 of 2 Seismnic WMIikdown CheCklist
('S.WC)Equipment ID No. :.I.- G Equip. Class 1 2 Z , Equipment Description
_$ r " " linteraction Effects, (v5Ec --vy/c es/ ,Z 7. Are soft targets free from impact-by nearby equipment or structures?
- 8. Afeýoverhead equipment, distribution Systems, ,ceiling tiles and lighting, and masonry block walls not likely tofcollapse onto the equipment?
- 9. Do attached lines have adequate flexibility to avoid d~amage?10. :Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic iteraction effects?YE] NO UCIO N/AD YE] NEr] UE] N/Ar]YEI ýNEI UE- N/Ar]YEI NEI Ur]Other Adverse Conditions
- 11. Haveyou looked for andifound no other seismic cotiditions that could YA.NE] UE[A adversely affect the safe tyfunctions of the eqdipment?
Comhments,(Additional pages may be added as necessary)
OM/ 't~~~ti~~~~¶LzP 621ptlLV4 M~ (. o=~Evaluated by:S. --: ( Jw" Date: /6 411 PAGE 178 of 668
,ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERS100NO PAGE 179 of 668 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSION 1.0 PAGE 180 of 668 TACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERS100NO PAGE 181 of 668
- ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSIO .0 oose boh PAGE 182 of 668 A ATTACHMENT 3: SEISMIC WALKIDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSION .0 I Ai i6 g PAGE 183 of 668 9 T ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERS1000 r~sn~g PAGE 184 of 668 3 ATTACHMENT 3: SEISMIC WALKIDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSION .0 PAGE 185 of 668 tACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSIONRO~oI~ on noc~Iats PAGE 186 of 668
- ACHMENT 3: SEISMIC WALKDOVVN CHECKLISTS 0 NO. SNCV061-RPT-01, VERSIOV.i recepta PAGE 187 of 668 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSION 1.0 Sheet I of 2 Status: QD N UýSeismic Walkdown Checklist (SWC)Equipment ID No. /-/..jjP -/' Equip. Class~2 Equipmjent Description SoL/D 5'7"-,7 / 7T -,YJ .e " 7-, IW ,1I 1 Locatjion:
Bldg. t'ry l, Floor El. .?2O Room, Area ,, /Manufacturer, Model, Etc. (optional'butreconmnended) -/A / -'O'.fE Instructlons for Completing Checklist This checklist may be used to document the results of the Seismic Walkd.own of anl. itemof eqmuipmentot .he SVEL. The space below each of the following questioiis'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 (ixe., is the.jtemn one: Y] MN of the050%,of SWEL items requiring
'such vetificati6n)?
-2; Is the anchorage free of bent, brokeni iussing or loose'hafdýVafr?
- 3. Is the anchorage free of corrosion that is more than mild surface oxidation?
- 4. Is the anchorage~freeof visible crack.s~ffinthe concrete near the ancIhors?5. Is the :anchorage configuration-consistent~with plant documentatii 0 (Note-: This-question only-applies ifthe item is ohe of the 50% for Which an anchorage configuration, eri~fication isrequired.)
- 6. Based on, the,:abovela'nht6ag-eeValiutis[, is the aiichofige freeof potentially adverse.seiIsmic conditions?
YK, NOE UE] N/AE Y], NE] UE] N/AX Yx NEI UE]12 Ente~r~the-cqiiipmentrcass nameý from,ýppcnaix B- Clases of Ecquil~riefr PAGE 188 of 668 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSION 1.0 Sheet 2 of 2 Seismic Walkdown Checklist (SWC)Equipment IDWNo. -Q' SPBEquip.
Class'2 ZQ EquiprnintDescription. t /?)ý -e ,ýOf 7 3Y" & -S 070?6:/1 5;.. .. ....... ... .in tferaction Effects 7. Are-soft targcts.free from impaqt by nearby equipment.orstructureS?
Y: NO UO NIAO 8.: Are overhead cquipment,,distribuhion'systemrs, ceiling tiles and lighting, NX NO U[J N/Ar and masonry blocklwalls not likelyto collapse ontod the eq-uipment?-
r '/x7;. R, /'L' 6EcfRA~o W.J., 9. Do attached lines have adequatepflexibility to avoid damage?NOI [JO N/AOI 10. Based on the~above seismic interaction evaluations; is equipment free Y)<,Nn uLJ of potentiadly adverse seismic interaetibn effects?pAfocv-at:
dOL- a.gE (: S4 VS',,/Sis
- Other AdverseConditions
- 11. Have you looked for and found no other:seismic conditionsthat could. Yg' NO UO adversely affect the safety functions of the equipment?
iCommint!ts (Additionia1 p'ageshay be added aý niecesary)
EvaluatedbytS 1ý911ý-P/I VI Date:; 2~ 02 PAGE 189 of 668 ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-01, VERSIOONO V, IBCOSP8 PAGE 190 of 668 A ATTACHMENT 3: SEISMIC WALKIDOWN CHECKLISTS 0 NO. SNCV061-RPT-01, VERSION 9.PAGE 191 of 668 3 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCVO61-RPT-01, VERS1IO0 PAGE 192 of 668 A ATTACHMENT 3: SEISMIC WALKIDOWN CHECKLISTS NO. SNCV061-RPT-01, VERS1000 PAGE 193 of 668