|
|---|
Category:Report
MONTHYEARRA-23-0313, Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation2023-12-14014 December 2023
Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation
RA-23-0141, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule2023-07-12012 July 2023
Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule
RA-23-0120, Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.22023-05-31031 May 2023
Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2
RA-23-0080, Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube2023-04-0505 April 2023
Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube
RA-22-0302, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)2022-11-0101 November 2022
Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)
RA-22-0239, Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary)2022-08-0909 August 2022
Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary)
RA-22-0017, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-01-0606 January 2022
Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
RA-21-0312, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)2021-11-22022 November 2021
Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)
IR 05000261/20210052021-08-25025 August 2021
Updated Inspection Plan for H. B. Robinson Steam Electric Plant, Unit 2 (Report 05000261/2021005)
RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019
Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46
RNP-RA/18-0024, Report of Changes Pursuant to 10 CFR 50.59(d)(2)2018-04-0202 April 2018
Report of Changes Pursuant to 10 CFR 50.59(d)(2)
RA-17-0040, Providing Methodology Reports DPC-NE-1008-P, Revision 0, DPC-NF-2010, Revision 3, and DPC-NE-2011-P, Revision 2. (Non-Proprietary Versions)2017-08-15015 August 2017
Providing Methodology Reports DPC-NE-1008-P, Revision 0, DPC-NF-2010, Revision 3, and DPC-NE-2011-P, Revision 2. (Non-Proprietary Versions)
ML16281A5102016-12-15015 December 2016
Staff Assessment of the Reactor Vessel Internals Aging Management Program Plans
RNP-RA/16-0087, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors2016-10-31031 October 2016
Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors
ML16280A2002016-10-0505 October 2016
Response to Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals
RNP-RA/16-0078, Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors2016-10-0505 October 2016
Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable High Range Containment Area Radiation Monitors
RA-16-0024, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P2016-10-0303 October 2016
Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P
RNP-RA/16-0073, Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits2016-09-14014 September 2016
Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits
RNP-RA/16-0038, Transition Report, Revision 1, Transition to National Fire Protection Association Standard 805, with Attachments a, I, J, L, M, and V. Pages 22-1742016-05-25025 May 2016
Transition Report, Revision 1, Transition to National Fire Protection Association Standard 805, with Attachments a, I, J, L, M, and V. Pages 22-174
RA-16-0023, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P2016-05-0404 May 2016
Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P
ML15253A4102016-03-11011 March 2016
Enclosure 2 Screening Analysis Report
RA-15-0042, Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis.2015-11-19019 November 2015
Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis.
RA-15-0047, Annual Report of Changes Pursuant to 10 CFR 50.462015-11-17017 November 2015
Annual Report of Changes Pursuant to 10 CFR 50.46
ML15280A1992015-10-19019 October 2015
Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review
RA-15-0031, Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors.2015-08-19019 August 2015
Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors.
RNP-RA/15-0053, Compliance Letter and Final Integrated Plan in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-04)2015-08-19019 August 2015
Compliance Letter and Final Integrated Plan in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-04)
RNP-RA/15-0018, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Power Range Neutron Flux Channel2015-02-26026 February 2015
Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Power Range Neutron Flux Channel
RNP-RA/14-0037, Response to NRC Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.4.12, Low Temperature Overpressure Protection System2014-04-0808 April 2014
Response to NRC Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.4.12, Low Temperature Overpressure Protection System
RNP-RA/14-0012, Flood Hazard Reevaluation Report, Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3....2014-03-12012 March 2014
Flood Hazard Reevaluation Report, Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3....
RNP-RA/14-0011, Revision to Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident2014-02-27027 February 2014
Revision to Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident
ML13365A2912014-02-19019 February 2014
Interim Staff Evaluation Regarding Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)
ML14027A0632014-01-24024 January 2014
Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for H. B. Robinson Steam Electric Plant, Unit 2, TAC No.: MF0720
ML13267A2122013-09-30030 September 2013
Enclosure 1, Transition Report - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition
ML13270A1762013-09-24024 September 2013
Redacted - Office of Nuclear Reactor Regulation (NRR) Reactor Systems Branch (Srxb) Support of Region II Inspection of H. B. Robinson Treatment of Voids in Systems That Are Important to Safety
RNP-RA/13-0079, Technical Specifications (TS) Section 5.8.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Wide Range Containment Pressure Transmitter2013-08-21021 August 2013
Technical Specifications (TS) Section 5.8.6, Post Accident Monitoring (PAM) Instrumentation Report, 14-Day Report for the Inoperability of the Wide Range Containment Pressure Transmitter
RNP-RA/13-0066, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for the Pressurizer Safety Valve Indication2013-06-24024 June 2013
Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for the Pressurizer Safety Valve Indication
RNP-RA/13-0037, Independent Spent Fuel Storage Installation, Annual Individual Exposure Monitoring Report for 20122013-04-25025 April 2013
Independent Spent Fuel Storage Installation, Annual Individual Exposure Monitoring Report for 2012
ML12331A1752012-11-26026 November 2012
Draft Bypass Fiber Quantity Test Plan
ML12278A3992012-08-31031 August 2012
WCAP-17077-NP, Rev 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant
ML1210707162012-05-17017 May 2012
Letter Report on the Evaluation of Cables from the HEAF Fire Event at the H.B. Robinson Steam Electric Plant
ML12068A1332012-02-23023 February 2012
Calculation RNP-M/MECH-1815, Revision 1, Evaluation of Emergency Diesel Generator Starting Capability at 150 PSIG
RNP-RA/11-0100, Annual Report of Changes to or Errors Discovered in an Acceptable Loss-of-Coolant Accident Evaluation Model Application for the Emergency Core Cooling System2011-11-23023 November 2011
Annual Report of Changes to or Errors Discovered in an Acceptable Loss-of-Coolant Accident Evaluation Model Application for the Emergency Core Cooling System
ML1124113592011-09-23023 September 2011
Final Precursor Analysis: Electrical Fault Causes Fire and Subsequent Reactor Trip with a Loss of Reactor Coolant Pump Seal Injection and Cooling
ML1124113582011-09-23023 September 2011
Final Precursor Analysis: Concurrent Unavailabilities - EDG B Inoperable Due to Failed Output Breaker and EDG a Unavailable Due to Testing and Maintenance
ML1128005282010-12-29029 December 2010
NRC 2011 Hb Robinson
ML1019304172010-05-0606 May 2010
Tritium Database Report
RNP-RA/09-0081, WCAP-17077-NP, Revision 0, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant.2009-07-31031 July 2009
WCAP-17077-NP, Revision 0, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant.
RNP-RA/09-0054, Attachments VI & VII to Serial: RNP-RA/09-0054 - Request for Technical Specifications Change to Section 3.3.1 Reactor Protection System Instrumentation2009-06-19019 June 2009
Attachments VI & VII to Serial: RNP-RA/09-0054 - Request for Technical Specifications Change to Section 3.3.1 Reactor Protection System Instrumentation
ML0821900132008-08-0707 August 2008
Monthly Operating Reports Second Quarter 2008
RNP-RA/08-0026, Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2008-03-0707 March 2008
Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
2023-07-12
[Table view]
Category:Technical
MONTHYEARRA-23-0313, Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation2023-12-14014 December 2023
Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation
RA-23-0141, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule2023-07-12012 July 2023
Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule
RA-23-0120, Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.22023-05-31031 May 2023
Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2
RA-23-0080, Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube2023-04-0505 April 2023
Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube
RA-22-0302, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)2022-11-0101 November 2022
Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)
RA-22-0239, Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary)2022-08-0909 August 2022
Technical Specifications Section 5.6.6. Post Accident Monitoring Instrumentation Report for Inoperable Safety Valve Position (Primary)
RA-22-0017, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-01-0606 January 2022
Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
RA-17-0040, Providing Methodology Reports DPC-NE-1008-P, Revision 0, DPC-NF-2010, Revision 3, and DPC-NE-2011-P, Revision 2. (Non-Proprietary Versions)2017-08-15015 August 2017
Providing Methodology Reports DPC-NE-1008-P, Revision 0, DPC-NF-2010, Revision 3, and DPC-NE-2011-P, Revision 2. (Non-Proprietary Versions)
ML16280A2002016-10-0505 October 2016
Response to Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals
RNP-RA/16-0073, Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits2016-09-14014 September 2016
Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits
RA-16-0023, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P2016-05-0404 May 2016
Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P
RA-15-0042, Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis.2015-11-19019 November 2015
Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis.
RA-15-0031, Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors.2015-08-19019 August 2015
Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors.
RNP-RA/14-0011, Revision to Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident2014-02-27027 February 2014
Revision to Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident
ML13365A2912014-02-19019 February 2014
Interim Staff Evaluation Regarding Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)
ML14027A0632014-01-24024 January 2014
Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for H. B. Robinson Steam Electric Plant, Unit 2, TAC No.: MF0720
ML13267A2122013-09-30030 September 2013
Enclosure 1, Transition Report - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition
ML13270A1762013-09-24024 September 2013
Redacted - Office of Nuclear Reactor Regulation (NRR) Reactor Systems Branch (Srxb) Support of Region II Inspection of H. B. Robinson Treatment of Voids in Systems That Are Important to Safety
ML12331A1752012-11-26026 November 2012
Draft Bypass Fiber Quantity Test Plan
ML12278A3992012-08-31031 August 2012
WCAP-17077-NP, Rev 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant
ML1210707162012-05-17017 May 2012
Letter Report on the Evaluation of Cables from the HEAF Fire Event at the H.B. Robinson Steam Electric Plant
ML12068A1332012-02-23023 February 2012
Calculation RNP-M/MECH-1815, Revision 1, Evaluation of Emergency Diesel Generator Starting Capability at 150 PSIG
RNP-RA/09-0081, WCAP-17077-NP, Revision 0, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant.2009-07-31031 July 2009
WCAP-17077-NP, Revision 0, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals at Robinson Nuclear Plant.
RNP-RA/09-0054, Attachments VI & VII to Serial: RNP-RA/09-0054 - Request for Technical Specifications Change to Section 3.3.1 Reactor Protection System Instrumentation2009-06-19019 June 2009
Attachments VI & VII to Serial: RNP-RA/09-0054 - Request for Technical Specifications Change to Section 3.3.1 Reactor Protection System Instrumentation
ML0821900132008-08-0707 August 2008
Monthly Operating Reports Second Quarter 2008
RNP-RA/06-0081, Steam Generator Alternate Repair Criteria for Tube Portion within the Tubesheet, WCAP-16627-NP2006-08-31031 August 2006
Steam Generator Alternate Repair Criteria for Tube Portion within the Tubesheet, WCAP-16627-NP
RNP-RA/06-0027, ANP-2512(NP), Loss of Forced Reactor Coolant Flow Analysis.2006-03-31031 March 2006
ANP-2512(NP), Loss of Forced Reactor Coolant Flow Analysis.
ML0507004082004-02-20020 February 2004
EMF-3030(NP), Revision 0, Robinson Nuclear Plant, Realistic Large Break LOCA Analysis, February 2004, Non-Proprietary Version
RNP-RA/03-0075, Technical Basis for RPV Head CRDM Nozzle Inspection Interval H.B. Robinson Steam Electric Plant, Unit No. 2, References 9-1 Through E-62003-07-31031 July 2003
Technical Basis for RPV Head CRDM Nozzle Inspection Interval H.B. Robinson Steam Electric Plant, Unit No. 2, References 9-1 Through E-6
RNP-RA/03-0031, Response to Request for Additional Information Re Application for Renewal of Operating License, Attachment III, Pages 356 - 5042003-04-28028 April 2003
Response to Request for Additional Information Re Application for Renewal of Operating License, Attachment III, Pages 356 - 504
ML0311207052003-04-18018 April 2003
Review of 90-day Steam Generator Tube Inservice Inspection Report for a Refueling Outage in 2001
ML0305202692003-02-15015 February 2003
Follow-up Report, Reference Event #39516
RNP-RA/03-0012, Request for Relief Pertaining to Examination Coverage Less than Essentially 100 Percent2003-02-11011 February 2003
Request for Relief Pertaining to Examination Coverage Less than Essentially 100 Percent
RNP-RA/02-0172, Steam Generator Tube Plugging During Refueling Outage 212002-11-11011 November 2002
Steam Generator Tube Plugging During Refueling Outage 21
RNP-RA/02-0164, Part 17 of 17, CD-ROM Providing the Review Tool Supporting the Application for Renewal of Operating License2002-11-0606 November 2002
Part 17 of 17, CD-ROM Providing the Review Tool Supporting the Application for Renewal of Operating License
ML0230402682002-09-19019 September 2002
Part 4 of 4 - Westinghouse Technology Manual, Course Outline for R-104P and Course Manual
ML0221103432002-01-31031 January 2002
Caldon, Inc Engineering Report: ER-267N, Bounding Uncertainty Analysis for Thermal Power Determination at CP&L Robinson Nuclear Power Station Using the LEFM Check Plus System
ML18288A3691990-10-31031 October 1990
ANF-88-054(NP)(A), PDC-3: Advanced Nuclear Fuels Corp Power Distribution Control for PWRs & Application of PDC-3 to Hb Robinson Unit 2.
NRC Generic Letter 1979-451979-09-25025 September 1979
NRC Generic Letter 1979-045: Transmittal of Reports Regarding Foreign Reactor Operation Experiences
2023-07-12
[Table view] |
Text
TABLE 3.5-2 TABLE 2 CONTAINMENTS, STRUCTURES, AND COMPONENT SUPPORT Component/Commodity Group Component Commodity Group Constituents:
Structure No 3070S01 Tank: Condensate Storage
- 3. Cable tray and conduit, Cable tray and conduit.
Electrical & Instrument Panels and Enclosures, Misc. Steel, Structural Steel, Electrical Component Supports Electrical component supports.
Structure No 4015S02 Bldg N/A: Intake Structure
- 3. Cable tray and conduit, Cable tray and conduit.
Electrical & Instrument Panels and Enclosures, Misc. Steel, Structural Steel, Electrical Component Supports Electrical & Instrument Panels and Enclosures.
Electrical component supports.
Instrument Racks and Frames.
Miscellaneous steel (Stairs & Ladders, platforms & connectors, grating &
checker Structure No 4060S01 Bldg N/A: North Service Water Header Enclosure
- 3. Cable tray and conduit, Cable tray and conduit.
Electrical & Instrument Panels and Enclosures, Misc. Steel, Structural Steel, Electrical Component Supports Electrical & Instrument Panels and Enclosures.
Electrical component supports.
Instrument Line Supports.
Miscellaneous steel (Stairs & Ladders, platforms & connectors, grating &
checker Structural steel (beams, plates, connectors, column)
Structure No 5100S01 Tank: Diesel Generator Fuel Oil Storage
- 3. Cable tray and conduit, Electrical & Instrument Panels and Enclosures.
Electrical & Instrument Panels and Enclosures, Misc. Steel, Structural Steel, Electrical Component Supports Electrical component supports.
Structure No 5100S02 Tank: DS Diesel Fuel Oil Wednesday, October 23, 2002 NRC: Table 3-x-2 Table 2 w/ Union Query Page 1 of 4
TABLE 3.5-2 TABLE 2 CONTAINMENTS, STRUCTURES, AND COMPONENT SUPPORT Component/Commodity Group Component Commodity Group Constituents:
- 3. Cable tray and conduit, Electrical & Instrument Panels and Enclosures.
Electrical & Instrument Panels and Enclosures, Misc. Steel, Structural Steel, Electrical Component Supports Electrical component supports.
Structure No 6110S01 Bldg N/A: Security Lighting
- 3. Cable tray and conduit, Electrical & Instrument Panels and Enclosures.
Electrical & Instrument Panels and Enclosures, Misc. Steel, Structural Steel, Electrical Component Supports Electrical component supports.
Structural steel (beams, plates, connectors, column)
Structure No 8300S18 Bldg 340: Dedicated Shutdown (DS) Diesel Generator Building
- 3. Cable tray and conduit, Cable tray and conduit.
Electrical & Instrument Panels and Enclosures, Misc. Steel, Structural Steel, Electrical Component Supports Electrical component supports.
Structure No 8300S36 Bldg 350: Turbine Building
- 3. Cable tray and conduit, Cable tray and conduit.
Electrical & Instrument Panels and Enclosures, Misc. Steel, Structural Steel, Electrical Component Supports Electrical & Instrument Panels and Enclosures.
Electrical component supports.
Structure No 8300S44 Electrical Manholes and Duct Banks
- 3. Cable tray and conduit, Cable tray and conduit.
Electrical & Instrument Panels and Enclosures, Misc. Steel, Structural Steel, Electrical Component Supports Electrical & Instrument Panels and Enclosures.
Electrical component supports.
Structure No 8300S48 Pipe Restraint Tower
- 3. Cable tray and conduit, Cable tray and conduit.
Electrical & Instrument Panels and Enclosures, Misc. Steel, Structural Steel, Electrical Component Supports Wednesday, October 23, 2002 NRC: Table 3-x-2 Table 2 w/ Union Query Page 2 of 4
TABLE 3.5-2 TABLE 2 CONTAINMENTS, STRUCTURES, AND COMPONENT SUPPORT Component/Commodity Group Component Commodity Group Constituents:
- 3. Cable tray and conduit, Electrical & Instrument Panels and Enclosures.
Electrical & Instrument Panels and Enclosures, Misc. Steel, Structural Steel, Electrical Component Supports Electrical component supports.
Structure No 8300S55 Bldg N/A: Miscellaneous Yard Structures
- 3. Cable tray and conduit, Cable tray and conduit.
Electrical & Instrument Panels and Enclosures, Misc. Steel, Structural Steel, Electrical Component Supports Electrical & Instrument Panels and Enclosures.
Electrical component supports.
Structure No 8320S01 Bldg 205: Reactor Auxiliary Building
- 3. Cable tray and conduit, Cable tray and conduit.
Electrical & Instrument Panels and Enclosures, Misc. Steel, Structural Steel, Electrical Component Supports Electrical & Instrument Panels and Enclosures.
Electrical component supports.
Component/Commodity Group Component Commodity Group Constituents:
Structure No 8010S01 Bldg 200: Reactor Containment Building
- 4. Reinforced Concrete Reinforced Concrete (Cylinder Wall, Dome, Basemat).
(Containment cylinder wall dome, basemat)
Component/Commodity Group Component Commodity Group Constituents:
Structure No 4015S02 Bldg N/A: Intake Structure
- 5. Electrical and Instrument Electrical & Instrument Panels and Enclosures.
Panels and Enclosures, Expansion Anchors, Siding, Louvers Expansion Anchors Protective Enclosure.
Siding.
Structure No 4060S01 Bldg N/A: North Service Water Header Enclosure
- 5. Electrical and Instrument Electrical & Instrument Panels and Enclosures.
Panels and Enclosures, Expansion Anchors, Siding, Louvers Wednesday, October 23, 2002 NRC: Table 3-x-2 Table 2 w/ Union Query Page 3 of 4
TABLE 3.5-2 TABLE 2 CONTAINMENTS, STRUCTURES, AND COMPONENT SUPPORT Component/Commodity Group Component Commodity Group Constituents:
Structure No 8300S18 Bldg 340: Dedicated Shutdown (DS) Diesel Generator Building
- 5. Electrical and Instrument Louvers Panels and Enclosures, Expansion Anchors, Siding, Louvers Protective Enclosure.
Structure No 8300S36 Bldg 350: Turbine Building
- 5. Electrical and Instrument Louvers Panels and Enclosures, Expansion Anchors, Siding, Louvers Protective Enclosure.
Siding.
Structure No 8300S46 Bldgs 215, 220 and 225: Fuel Handling Building
- 5. Electrical and Instrument Siding.
Panels and Enclosures, Expansion Anchors, Siding, Louvers Structure No 8320S01 Bldg 205: Reactor Auxiliary Building
- 5. Electrical and Instrument Louvers Panels and Enclosures, Expansion Anchors, Siding, Louvers Siding.
Component/Commodity Group Component Commodity Group Constituents:
Structure No 8300S09 Bldg 210: Radwaste Building
- 7. Seismic Joint Filler Seismic joint filler Structure No 8300S46 Bldgs 215, 220 and 225: Fuel Handling Building
- 7. Seismic Joint Filler Seismic joint filler Structure No 8320S01 Bldg 205: Reactor Auxiliary Building
- 7. Seismic Joint Filler Seismic joint filler Component/Commodity Group Component Commodity Group Constituents:
Structure No 8320S01 Bldg 205: Reactor Auxiliary Building
- 8. Roof (Membrane or Built Up) Roof (Membrane or Built Up)
Wednesday, October 23, 2002 NRC: Table 3-x-2 Table 2 w/ Union Query Page 4 of 4
