Letter Sequence Response to RAI |
---|
TAC:ME4640, Steam Generator Tube Integrity (Approved, Closed) |
Results
- Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval
Other: L-11-114, Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples, L-11-131, Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems., L-11-334, Reply to Request Additional Information for the Review of the License Renewal Application Amendment No. 21, L-12-337, Review of the Safety Evaluation Report with Open Items Related to the License Renewal, L-12-444, Submittal of Contractor Equivalent Margins Assessments for Reactor Vessel Welds (Nonproprietary Versions), L-12-456, Notification of Closure of Commitments Related to the Review of the License Renewal Application, L-13-257, Notification of Completion of a License Renewal Commitment Related to the Review of License Renewal Application TAC No. ME4640) and License Renewal Application Amendment No. 45), L-13-330, License Renewal Application Amendment No. 46 - Annual Update, L-13-341, Review of the Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station, L-14-085, License Renewal Application (TAC No. ME4640) Amendment No. 48, L-14-206, License Renewal Application Amendment No. 50 - Annual Update, L-15-120, Notification of Completion of License Renewal Commitments Related to the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application and License Renewal Application Amendment No. 55, L-15-139, License Renewal Reactor Vessel Internals Inspection Plan, L-15-214, License Renewal Application Amendment No. 59 - Annual Update, L-15-309, License Renewal Application Amendment No. 60, L-15-310, C-CSS-099.20-069, Rev 0, Shield Building Laminar Cracking Limits., ML102450565, ML111050091, ML11110A089, ML11110A091, ML11110A092, ML11110A093, ML11110A094, ML11110A095, ML11110A105, ML11110A106, ML11110A107, ML11122A014, ML11126A017, ML11126A018, ML11126A019, ML11126A020, ML11126A021, ML11126A022, ML11126A023, ML11126A024, ML11126A025, ML11126A026, ML11126A032, ML11126A033, ML11126A034, ML11126A035, ML11126A036, ML11126A037, ML11126A038, ML11126A039, ML11126A040, ML11126A041, ML11126A042, ML11126A043... further results
|
MONTHYEARML11126A0882008-01-12012 January 2008 Drawing No. LR-M041B, Revision 1, Piping & Instrument Diagram Primary Service Water System. Job Code 12501 Project stage: Other ML11126A0902008-01-15015 January 2008 Drawing No. LR-OS41A1, Revision 1, Operational Schematic Emergency Diesel Generator Systems. Project stage: Other L-11-131, Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems.2008-01-15015 January 2008 Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems. Project stage: Other ML11126A0682008-05-0505 May 2008 Drawing No. LR-M-037E, Revision 28, Piping & Instrument Diagram Clean Liquid Radioactive Waste System. Project stage: Other ML11126A0652008-08-0606 August 2008 Drawing No. LR-M036B, Revision 1, Piping & Instrument Diagram Component Cooling Water System. Project stage: Other ML11126A0592008-10-0909 October 2008 Drawing No. LR-M033A, Revision 1, Piping & Instrument Diagram High Pressure Injection. Project stage: Other ML11126A0632008-10-10010 October 2008 Drawing No. LR-M033B, Revision 1, Piping & Instrument Diagram Decay Heat Train 1. Project stage: Other ML11126A0702008-10-10010 October 2008 Drawing No. LR-M033C, Revision 1, Piping & Instrument Diagram Decay Heat Train 2. Project stage: Other ML11126A0742008-11-0606 November 2008 Drawing No. LR-M043, Revision 1, Piping & Instrument Diagram Auxiliary Building Chilled Water System. Project stage: Other ML11126A0832008-12-18018 December 2008 Drawing No. LR-M038C, Revision 2, Piping & Instrument Diagram Gaseous Radioactive Waste System. Job Code 12501 Project stage: Other ML11126A0712009-04-0707 April 2009 Drawing No. LR-M034, Revision 1, Piping & Instrument Diagram Emerg. Core Cooling System Ctmt. Spray & Core Flooding Systems. Project stage: Other ML11126A0892009-04-0707 April 2009 Drawing No. LR-OS002, Revision 1, Operational Schematic Makeup and Purification System. Project stage: Other ML1024505652010-08-27027 August 2010 License Renewal Application and Ohio Coastal Management Program Consistency Certification Project stage: Other ML1104500462011-02-17017 February 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Fire Protection Project stage: RAI ML11126A0792011-02-25025 February 2011 Drawing No. LR-M900A, Revision 0, Instrument Air System Piping Schematic. Project stage: Other ML1104205972011-02-28028 February 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Section 2.4 Project stage: RAI ML1106801722011-03-17017 March 2011 Request for Additional Information on the Reactor Vessel Surveillance Aging Management Program, Time-Limited Aging Analyses for Neutron Embrittlement of the Rv and Internals, and Other TLAAs for the Review of the Davis-Besse Nuclear Power S Project stage: RAI ML1107007322011-03-18018 March 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station-Section 2.2 & 2.3 Project stage: RAI L-11-078, Reply to Request for Additional Information for the Review of License Renewal Application (TAC ME4640) Amendment No. 12011-03-18018 March 2011 Reply to Request for Additional Information for the Review of License Renewal Application (TAC ME4640) Amendment No. 1 Project stage: Response to RAI ML11068A0002011-03-21021 March 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Section 4.7 (TAC Number ME4640) Project stage: RAI L-11-079, Reply to Request for Additional Information for the Review of the License Renewal Application2011-03-23023 March 2011 Reply to Request for Additional Information for the Review of the License Renewal Application Project stage: Response to RAI L-11-089, Reply to Request for Additional Information for the Review License Renewal Application2011-03-23023 March 2011 Reply to Request for Additional Information for the Review License Renewal Application Project stage: Response to RAI ML1108206242011-03-30030 March 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station-Section 2.1 (Tac No. ME4640) Project stage: RAI ML1109002952011-03-31031 March 2011 Safety Evaluation Report Related to the License Renewal of Salem Nuclear Generating Station Project stage: Approval ML1108204902011-04-0505 April 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Batch 1 Project stage: RAI ML11110A0932011-04-15015 April 2011 Drawing No. M-037D, Rev. 21, Clean Liquid Radioactive Waste System Project stage: Other ML11110A1072011-04-15015 April 2011 Drawing No. M-045, Rev. 56, Chemical Addition Systems Project stage: Other ML11110A1062011-04-15015 April 2011 Drawing No. M-042C, Rev. 33, Sampling System Sh. 3 Project stage: Other ML11110A1052011-04-15015 April 2011 Drawing No. M-040A, Rev. 76, Reactor Coolant System Details Project stage: Other ML11110A0952011-04-15015 April 2011 Drawing No. M-039B, Rev. 18, Miscellaneous Liquid Radioactive Waste Project stage: Other ML11110A0942011-04-15015 April 2011 Drawing No. M-039A, Rev. 33, Miscellaneous Liquid Radioactive Waste Project stage: Other ML11110A0922011-04-15015 April 2011 Drawing No. M-037C, Rev. 30, Clean Liquid Radioactive Waste System Project stage: Other L-11-114, Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples2011-04-15015 April 2011 Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples Project stage: Other L-11-107, Reply to Request for Additional Information on Reactor Vessel Surveillance Aging Management Program & Time-Limited Aging Analyses for Neutron Embrittlement for Review of License Renewal Application & License Renewal Application...2011-04-15015 April 2011 Reply to Request for Additional Information on Reactor Vessel Surveillance Aging Management Program & Time-Limited Aging Analyses for Neutron Embrittlement for Review of License Renewal Application & License Renewal Application... Project stage: Response to RAI ML11110A0882011-04-15015 April 2011 Reply to Request for Additional Information for the Review of the License Renewal Application, Sections 2.2 & 2.3, License Renewal Application Amendment No. 3, and Revised License Renewal Project stage: Response to RAI ML11110A0912011-04-15015 April 2011 Drawing No. M-011, Rev. 61, Domestic Water System Project stage: Other ML11110A0892011-04-15015 April 2011 Drawing No. M-0060, Rev. 52, Auxiliary Feedwater System Project stage: Other ML1110500912011-04-19019 April 2011 Scoping and Screening Audit Report Regarding the Davis-Besse Nuclear Power Station License Renewal Application Project stage: Other L-11-115, Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 42011-04-20020 April 2011 Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 4 Project stage: Response to RAI ML1109807182011-04-20020 April 2011 Request for Additional Information for the Review of the Davis-Bessie Nuclear Power Station - Batch 2 Project stage: RAI ML11126A0362011-04-29029 April 2011 Drawing No. LR-M017D, Revision 1 Piping & Instrument Diagram, Steam Blackout Diesel Generator. Project stage: Other ML11126A0352011-04-29029 April 2011 Drawing No. LR-M017C, Revision 2, Piping & Instrument Diagram, Fuel Oil. Project stage: Other ML11126A0342011-04-29029 April 2011 Drawing No. LR-M017B, Revision 1, Piping & Instrument Diagram, Diesel Generators Air Start. Project stage: Other ML11126A0332011-04-29029 April 2011 Drawing No. LR-M016B, Revision 1, Piping & Instrument Diagram Station Fire Protection System Project stage: Other ML11126A0322011-04-29029 April 2011 Drawing No. LR-M016A, Revision 1, Piping & Instrument Diagram Station Fire Protection System Project stage: Other ML11126A0262011-04-29029 April 2011 Drawing No. LR-M010C, Revision 1, Piping & Instrument Diagram Make-up Water Treatment System Project stage: Other ML11126A0252011-04-29029 April 2011 Drawing No. LR-M010A, Revision 1, Piping & Instrument Diagram Make-Up Water Treatment System Project stage: Other ML11126A0242011-04-29029 April 2011 Drawing No. LR-M009B, Revision 1, Piping & Instrument Diagram Cooling Water System Project stage: Other ML11126A0192011-04-29029 April 2011 Drawing No. LR-M003A, Revision 1, Piping & Instrument Diagram Main Steam and Reheat System. Sheet 1 Project stage: Other ML11126A0452011-04-29029 April 2011 Drawing No. LR-M024H, Revision 1, Piping & Instrument Diagram, No. 2 Main and Auxiliary Turbine Driven Feed Pumps. Project stage: Other 2011-02-25
[Table View] |
|
---|
Category:Letter type:L
MONTHYEARL-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule L-24-032, Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report2024-07-15015 July 2024 Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report L-24-063, License Amendment Request to Remove the Table of Contents from the Technical Specifications2024-07-0808 July 2024 License Amendment Request to Remove the Table of Contents from the Technical Specifications L-24-024, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-19019 June 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-214, Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2024-06-0505 June 2024 Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements L-24-019, Unit No.1 - Report of Facility Changes, Tests, and Experiments2024-05-22022 May 2024 Unit No.1 - Report of Facility Changes, Tests, and Experiments L-24-072, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 20232024-05-15015 May 2024 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 2023 L-24-111, Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-05-15015 May 2024 Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations L-24-031, Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage2024-05-14014 May 2024 Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage L-24-069, Occupational Radiation Exposure Report for Year 20232024-04-30030 April 2024 Occupational Radiation Exposure Report for Year 2023 L-24-018, Submittal of Core Operating Limits Report, Cycle 24, Revision 02024-04-16016 April 2024 Submittal of Core Operating Limits Report, Cycle 24, Revision 0 L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024 Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023 Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation L-23-215, Changes to Emergency Plan2023-10-19019 October 2023 Changes to Emergency Plan L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023 Submittal of Fifth Ten Year Inservice Testing Program L-23-034, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-13013 June 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-135, Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-31031 May 2023 Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report L-23-101, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 20222023-05-12012 May 2023 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 2022 L-23-131, Readiness for Resumption of NRC Supplemental Inspection2023-05-12012 May 2023 Readiness for Resumption of NRC Supplemental Inspection L-23-092, Occupational Radiation Exposure Report for Year 20222023-04-27027 April 2023 Occupational Radiation Exposure Report for Year 2022 L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports L-23-037, and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2023-03-29029 March 2023 and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023 Annual Notification of Property Insurance Coverage L-23-059, Response to Apparent Violation in NRC Inspection Report 05000346/2022091; EA 23-0022023-03-0909 March 2023 Response to Apparent Violation in NRC Inspection Report 05000346/2022091; EA 23-002 L-22-212, CFR 50.55a Request RP-5 Regarding Inservice Pump Testing2023-03-0606 March 2023 CFR 50.55a Request RP-5 Regarding Inservice Pump Testing L-23-048, Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2023-03-0101 March 2023 Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report L-23-057, Energy Harbor Nuclear Corp Retrospective Premium Guarantee2023-02-20020 February 2023 Energy Harbor Nuclear Corp Retrospective Premium Guarantee L-22-253, Submittal of Pressure and Temperature Limits Report, Revision 52023-01-10010 January 2023 Submittal of Pressure and Temperature Limits Report, Revision 5 L-22-284, Request for Notice of Enforcement Discretion for Technical Specification 3.7.9, Ultimate Heat Sink (UHS)2022-12-28028 December 2022 Request for Notice of Enforcement Discretion for Technical Specification 3.7.9, Ultimate Heat Sink (UHS) L-22-211, Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2022-09-29029 September 2022 Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report L-22-216, Submittal of Pressure and Temperature Limits Report. Revision 42022-09-27027 September 2022 Submittal of Pressure and Temperature Limits Report. Revision 4 L-22-213, Occupational Radiation Exposure Report for Year 2021 - Correction2022-09-23023 September 2022 Occupational Radiation Exposure Report for Year 2021 - Correction L-22-129, Submittal of the Updated Final Safety Analysis Report, Revision 342022-09-20020 September 2022 Submittal of the Updated Final Safety Analysis Report, Revision 34 L-22-194, Submittal of Supplemental Information for the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events2022-09-19019 September 2022 Submittal of Supplemental Information for the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events L-22-203, Submittal of Evacuation Time Estimates2022-09-12012 September 2022 Submittal of Evacuation Time Estimates L-22-050, Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual2022-08-0909 August 2022 Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual L-22-152, Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan2022-07-0505 July 2022 Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan L-22-068, Cycle 22 and Refueling Outage 22 Inservice Inspection Summary Report2022-06-30030 June 2022 Cycle 22 and Refueling Outage 22 Inservice Inspection Summary Report L-22-037, 2021 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2022-06-30030 June 2022 2021 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-22-149, Post Accident Monitoring Report2022-06-23023 June 2022 Post Accident Monitoring Report L-22-153, Readiness for NRC Supplemental Inspection Required for a White Finding2022-06-22022 June 2022 Readiness for NRC Supplemental Inspection Required for a White Finding L-22-098, Withdrawal of Proposed Inservice Inspection Alternative RR-A22022-06-22022 June 2022 Withdrawal of Proposed Inservice Inspection Alternative RR-A2 2024-08-27
[Table view] |
Text
FENOC FE O 5501 North State Route 2 FirstEnergyNuclear Operating Company Oak Harbor,Ohio 43449 Barry S. Allen 419-321-7676 Vice President - Nuclear Fax: 419-321-7582 March 18, 2011 L-1 1-078 10 CFR 54 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station, Unit No. 1 Docket No. 50-346, License No. NPF-3 Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 1 By letter dated August 27, 2010, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102450565), FirstEnergy Nuclear Operating Company (FENOC) submitted an application pursuant to Title 10 of the Code of Federal Regulations, Part 54 for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station (DBNPS), Unit Number 1. By letter dated February 17, 2011 (ADAMS Accession No. ML110450046), the Nuclear Regulatory Commission (NRC) requested additional information to complete its review of the License Renewal Application (LRA).
The Attachment provides the FENOC reply to the NRC request for additional information.
The NRC request is shown in bold text followed by the FENOC response. The Enclosure provides Amendment No. 1 to the DBNPS LRA.
There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Clifford I. Custer, Fleet License Renewal Project Manager, at (724) 682-7139.
Davis-Besse Nuclear Power Station, Unit No. 1 L-1 1-078 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on March ___, 2011.
Sincerely, Barry S. Hen
Attachment:
Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application
Enclosure:
Amendment No. 1 to the DBNPS License Renewal Application cc: NRC DLR Project Manager NRC Region III Administrator cc: w/o Attachment or Enclosure NRC DLR Director NRR DORL Project Manager NRC Resident Inspector Utility Radiological Safety Board
Attachment L-11-078 Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application, Section 2.3.3.14 Page 1 of 5 Section 2.3.3.14 RAI 2.3.3.14-1 License renewal application (LRA) drawing LR-MO16A shows that several yard fire hydrants and post indicator valves are out of scope (i.e., not colored in green). The staff believes that yard fire hydrants and post indicator valves have the fire protection intended functions required to be compliant with 10 CFR 50.48 as stated in 10 CFR 54.4. The fire hydrants and post indicator valves also serve as the pressure boundary for the fire protection water supply system.
The staff requests that the applicant verify whether the yard hydrants and post indicator valves are in the scope of license renewal in accordance with 10 CFR 54.4(a) and whether they are subject to an aging management review (AMR) in accordance with 10 CFR 54.21(a)(1). If they are excluded from the scope of license renewal and are not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.
RESPONSE RAI 2.3.3.14-1 The fire hydrants and post indicator valves (and other components) highlighted in green on license renewal (LR) drawing LR-M01 6A provide for protection of Davis-Besse Nuclear Power Station Fire Hazards Analysis Report (FHAR) fire areas that are defined as Branch Technical Position (BTP) APCSB 9.5-1, Appendix A areas. Therefore, these hydrants and post indicator valves are within the scope of license renewal for Fire Protection (10 CFR 50.48) and are subject to aging management review in accordance with 10 CFR 54.21(a)(1). The yard hydrants and post indicator valves that are not highlighted in green on license renewal drawing LR-M016A are not credited in the FHAR and are, therefore, out of scope for license renewal.
The yard hydrants and post indicator valves (and other components) that are not highlighted in green also do not serve as part of the license renewal pressure boundary for the fire protection water supply system components that are in scope for license renewal. The license renewal pressure boundary function is fulfilled by the hydrants, post indicator valves, other valves and other components that are highlighted in green on license renewal drawing LR-MO16A.
The bases for the scoping determinations are described below.
The manual fire suppression system components such as hose stations, connections, hydrants and hydrant hose houses that are necessary to meet BTP APCSB 9.5-1, Appendix A, commitments are addressed in Section 8.2 of the Davis-Besse FHAR. The
Attachment L-11-078 Page 2 of 5 hydrants highlighted on license renewal drawing LR-MO16A are within the scope of license renewal for Fire Protection (10 CFR 50.48) and are subject to aging management review in accordance with 10 CFR 54.21(a)(1). Those in-scope hydrants, listed below, were identified by an evaluation of the information provided in the FHAR.
Hydrant LR-M016A Number Coordinate Location in Plant H-1 E-7 Northwest of Water Treatment Building (provides coverage for Water Treatment Building, Intake Structure, Pump House, Turbine Building, Transformer, etc.)
H-2 E-10 East of Office Building (provides coverage for Water Treatment Building, Intake Structure, Pump House, Turbine Building, etc.)
H-3 F-11 Southeast Corner of Maintenance Shop (provides coverage for Water Treatment Building, Intake Structure, Pump House, Turbine Building, etc.)
H-1 3 K-7 West of Number 2 Startup Transformer (provides coverage for Auxiliary Building, Transformers, etc.)
H-1 5 J-6 North of Number 2 Startup Transformer (provides coverage for Auxiliary Building, Transformers, Diesel Fuel Oil Week Tanks, etc.)
H-1 6 F-6 North of Turbine Train Bay (provides coverage for Pump House, Turbine Building, Transformers, etc.)
The hydrants listed above were determined to be within the scope of license renewal for Fire Protection (10 CFR 50.48) by evaluating Section 8.2.4 and Table 8-6 of the FHAR, which specifically identify hydrants required to be operable for protection of the FHAR fire areas defined as BTP APCSB 9.5-1, Appendix A areas.
Fire water branch lines to yard hydrants not identified above are highlighted up to the first accessible valve capable of providing isolation of the branch line from the fire water fire main loop. While the majority of these yard hydrants have a post indicator valve which provides isolation capability from the fire main loop, not all the branch lines to these out-of-scope yard hydrants are provided with a post indicator valve. In such cases, a non-post indicator valve (i.e., curb valve) is relied upon to provide isolation and provides the pressure boundary integrity of the fire main loop.
Attachment L-1 1-078 Page 3 of 5 RAI 2.3.3.14-2 LRA drawing LR-MO16B shows that the automatic sprinkler system for the No. 1 Diesel Generator Room is in the scope of license renewal and subject to an AMR.
However, the automatic sprinkler system for the No. 2 Diesel Generator Room does not appear in the LRA drawings as being in the scope of license renewal and subject to an AMR.
The staff requests that the applicant verify whether the automatic sprinkler system for the No. 2 Diesel Generator Room is in the scope of license renewal in accordance with 10 CFR 54.4(a) and subject to an AMR in accordance with 10 CFR54.21(a)(1). If the sprinkler system is excluded from the scope of license renewal and not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.
RESPONSE RAI 2.3.3.14-2 As shown on LRA drawing LR-MI016B (coordinate F-4), the automatic sprinkler system for the No. 1 Diesel Generator Room is within the scope of license renewal. As shown on LRA drawing LR-M016B (coordinate G-4), the automatic sprinkler system for the No. 2 Diesel Generator Room is within the scope of license renewal. Both automatic sprinkler systems are within the scope of license renewal in accordance with 10 CFR 54.4(a) and subject to aging management review in accordance with 10 CFR 54.21(a)(1).
Attachment L-1 1-078 Page 4 of 5 RAI 2.3.3.14-3 Tables 2.3.3-14 and 3.3.2-14 of the LRA do not include the following fire protection components:
fire hose stations, fire hose connections, and hose racks sprinkler heads floor drains for the fire water dikes and curbs for the oil spill confinement components in reactor coolant pump oil collection system The staff Requests that the applicant verify whether the fire protection components listed above are in the scope of license renewal in accordance with 10 CFR 54.4(a) and whether they are subject to an AMR in accordance with 10 CFR 54.21(a)(1). If they are excluded from the scope of license renewal and are not subject to an AMR, the staff requests that the applicant provide justification for the exclusion.
RESPONSE RAI 2.3.3.14-3 The fire protection components (i.e., fire hose stations, fire hose connections, and hose racks, sprinkler heads, floor drains for fire water, dikes and curbs for oil spill confinement, and components in the reactor coolant pump oil collection system) identified in the NRC request are in the scope of license renewal in accordance with 10 CFR 54.4(a) and the passive, long-lived components are subject to aging management review (AMR) in accordance with 10 CFR 54.21(a)(1), as clarified below:
- Fire hose stations, fire hose connections, and hose racks that are in the scope of license renewal and subject to AMR are comprised of piping and piping components, valve bodies, and equipment structural supports. At Davis-Besse, there are five types of fire hose stations: hose reels, hose racks, hose cabinets (surface-mounted and recessed), and hose connections. Each station type is comprised of piping (including a standpipe riser) with a normally-closed angle valve to which the hose is connected, and a normally-open isolation valve to the building header. Fire Protection System component types "Piping" and "Valve Body" are listed in LRA Tables 2.3.3-14 and 3.3.2-14, and include those types of fire protection hose station components required for compliance with 10 CFR 50.48. License renewal drawings LR-MO16A and LR-MO16B depict the evaluation boundaries for the subject piping and piping components and valve bodies within the scope of license renewal.
Component type "Equipment Component Supports" is listed with the Bulk Commodities in LRA Tables 2.4-13 and 3.5.2-13, and includes the cabinets and racks associated with hose stations required for compliance with 10 CFR 50.48.
Attachment L-1 1-078 Page 5 of 5 Fire hoses (and their integral connections) are in the scope of license renewal, but are periodically replaced. Therefore, the fire hoses are not subject to AMR, as outlined in 10 CFR 54.21(a)(1)(i) and (ii).
- Sprinkler heads are included in Fire Protection System LRA Tables 2.3.3-14 and 3.3.2-14 as component type "Spray Nozzle."
" Floor drains for fire water (i.e., floor drains located in areas with in-scope fire protection sprinkler systems or hose stations) were included with other floor drain components as component type "Piping" within the evaluation boundaries of the Station Plumbing, Drains, and Sumps System (SPDSS), and are listed in LRA Tables 2.3.3-31 and 3.3.2-31. License renewal drawing LR-M090 depicts the evaluation boundaries for the subject piping and piping components within the scope of license renewal.
For Davis-Besse, the in-scope floor drains have been included in the scope of license renewal in accordance with 10 CFR 54.4(a)(2) because they are located in buildings or areas where their failure could prevent the satisfactory accomplishment of a safety function as defined in 10 CFR 54.4(a)(1), and were assigned a "Structural integrity" component intended function.
" Dikes and curbs for oil spill confinement are included with Yard Structures as component type "Diesel Oil Storage Tank Retaining Area and Dike" in LRA Tables 2.4-12 and 3.5.2-12, and with Bulk Commodities as concrete component type "Flood Curbs" in LRA Tables 2.4-13 and 3.5.2-13.
During the development of the response for this NRC request, FENOC identified that the concrete component type Flood Curbs incorrectly excluded the intended function "SRE" (support for criterion (a)(3) equipment), and instead included only the FLB (flood barrier) and SNS (support for criterion (a)(2) equipment) intended functions. LRA Tables 2.4-13 and 3.5.2-13 are revised to include SRE (support for criterion (a)(3) equipment) as an intended function for concrete component type Flood Curbs.
See the Enclosure to this letter for the revision to the Davis-Besse LRA.
" Components in reactor coolant pump oil collection system are included within the non-Class 1 evaluation boundaries of the Reactor Coolant System and are listed in LRA Tables 2.3.1-3 and 3.1.2-3 as component types "Drain Pan", "Flexible Connection", "Piping", "Tank (DB-T156-1 and DB-T156-2)", and "Valve Body".
License renewal drawing LR-M040D depicts the evaluation boundaries for the subject drain pans, piping, flexible connections, tanks, and valves within the scope of license renewal.
Enclosure Davis-Besse Nuclear Power Station (DBNPS), Unit No. 1 Letter L-11-078 Amendment No. 1 to the DBNPS License Renewal Application Page 1 of 2 License Renewal Application Sections Affected Table 2.4-13 Table 3.5.2-13 The Enclosure identifies the change to the License Renewal Application (LRA) by Affected LRA Section, LRA Page No., and Affected Paragraph and Sentence. The count for the affected paragraph, sentence, bullet, etc. starts at the beginning of the affected Section or at the top of the affected page, as appropriate. Below each section the reason for the change is identified, and the sentence affected is printed in italics with deleted text Mqed-u and added text underlined.
Enclosure L-1 1-078 Page 2 of 2 Affected Paragraph Affected LRA Section LRA Page No. and Sentence Table 2.4-13 Page 2.4-51 Concrete Flood Curbs row The License Renewal Application is amended as follows to include SRE (support for criterion (a)(3) equipment) as an intended function for concrete flood curbs:
Table 2.4-13 Bulk Commodities Components Subject to Aging Management Review CompnentTypeIntended Function CompnentType(as defined in Table 2.0-1)
Concrete Components Flood Curbs FLB, SNS, SRE Table 3.5.2-13 Page 3.5-158 Row 173, Flood Curbs The License Renewal Application is amended as follows to include SRE (support for criterion (a)(3) equipment) as an intended function for concrete flood curbs:
Table 3.5.2-13 Aging Management Review Results - Bulk Commodities Row Component / Intended No. Commodity Function1 Concrete 173 Flood Curbs FLB, SNS, SRE