Letter Sequence RAI |
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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
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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
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Category:Letter
MONTHYEARIR 05000346/20243012024-02-0202 February 2024 NRC Initial License Examination Report 05000346/2024301 IR 05000346/20230042024-01-31031 January 2024 Integrated Inspection Report 05000346/2023004 ML23313A1352024-01-17017 January 2024 Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program ML23353A1192023-12-19019 December 2023 Operator Licensing Examination Approval Davis Besse Nuclear Power Station, January 2024 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 ML23338A3172023-12-0606 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001 IR 05000346/20234032023-11-0202 November 2023 Security Baseline Inspection Report 05000346/2023403 ML23293A0612023-11-0101 November 2023 Letter to the Honorable Marcy Kaptur, from Chair Hanson Responds to Letter Regarding Follow Up on Concerns Raised by Union Representatives During the June Visit to the Davis-Besse Nuclear Power Plant L-23-215, Changes to Emergency Plan2023-10-19019 October 2023 Changes to Emergency Plan ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure IR 05000346/20234012023-09-13013 September 2023 Security Baseline Inspection Report 05000346/2023401 (Public) 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 IR 05000346/20230112023-08-30030 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000346/2023011 ML23129A1722023-08-25025 August 2023 Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1 IR 05000346/20230052023-08-24024 August 2023 Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2023005) 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 IR 05000346/20230502023-08-0303 August 2023 Special Inspection Report 05000346/2023050 IR 05000346/20230902023-08-0101 August 2023 EA-23-002 Davis-Besse Nuclear Power Station - NRC Inspection Report No. 05000346/2023090 (Public) ML23178A2742023-08-0101 August 2023 Letter to the Honorable Marcy Kaptur from Chair Hanson Responds to Letter Regarding the License Transfer Application for the Davis-Besse Nuclear Power Station L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023 Submittal of Fifth Ten Year Inservice Testing Program IR 05000346/20230022023-07-27027 July 2023 Integrated Inspection Report 05000346/2023002 ML23193A7842023-07-13013 July 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000346/2023402 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III ML23160A2342023-06-13013 June 2023 Confirmation of Initial License Examination 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 IR 05000346/20235012023-06-13013 June 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000346/2023501 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 ML23124A1742023-05-17017 May 2023 Energy Harbor Fleet Vistra License Transfer - Request for Withholding Information from Public Disclosure for Commance Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 ML23129A0112023-05-16016 May 2023 Notice of Consideration of Approval of Indirect and Direct License Transfer for Comanche Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 (EPID L-2023-LLM-0000) (Letter) ML23131A2732023-05-15015 May 2023 Notification of NRC Supplemental Inspection 95001 and Request for Information 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 IR 05000346/20230102023-05-0909 May 2023 Commercial Grade Dedication Inspection Report 05000346/2023010 ML23123A1272023-05-0303 May 2023 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Davis-Besse Nuclear Power Station IR 05000346/20230012023-05-0101 May 2023 Integrated Inspection Report 05000346/2023001 and 07200014/2022001 L-23-092, Occupational Radiation Exposure Report for Year 20222023-04-27027 April 2023 Occupational Radiation Exposure Report for Year 2022 ML23111A1972023-04-26026 April 2023 Information Meeting with Question and Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of Davis-Besse Nuclear Power Plant Station ML23114A1062023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection CP-202300181, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-20020 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments CP-202300157, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-14014 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML23096A1382023-04-11011 April 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report 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 ML23066A2892023-03-14014 March 2023 Request for Threshold Determination Under 10 CFR 50.80 and 10 CFR 72.50 for an Amendment to the Voting Agreement ML23066A2592023-03-14014 March 2023 Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2, Davis Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit 1 2024-02-02
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23338A3172023-12-0606 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001 ML23193A7842023-07-13013 July 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000346/2023402 ML23131A2732023-05-15015 May 2023 Notification of NRC Supplemental Inspection 95001 and Request for Information ML23033A0322023-02-0101 February 2023 NRR E-mail Capture - Request for Additional Information for Davis-Besse's 2022 Steam Generator Inspection Report (L-2022-LRO-0115) ML22357A0302022-12-23023 December 2022 Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000346/2023010 ML22266A1102022-09-23023 September 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding July 21, 2022, Request for Withholding Information from Public Disclosure ML22214A7042022-08-0202 August 2022 Reissue - Davis-Besse Nuclear Power Station, Unit 1 Notification of Nrc Fire Protection Team Inspection Request for Information: Inspection Report 05000346/2022011 ML22187A0992022-07-0606 July 2022 Notification of NRC Supplemental Inspection (95001) and Request for Information ML22164A8572022-06-13013 June 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan ML22118A6862022-04-28028 April 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Alternative to Extend the Steam Generator Weld Inspection Interval ML22112A1092022-04-22022 April 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building ML22055A0872022-02-23023 February 2022 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Relief Request RP-3 IR 05000346/20210912021-12-17017 December 2021 NRC Inspection Report (05000346/2021091) Preliminary Greater than Green Finding ML21321A3792021-11-16016 November 2021 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Alternative to Extend the Steam Generator Weld Inspection Interval ML21301A0992021-10-28028 October 2021 Draft Request for Additional Information: Proposed Alternate for Examination of Steam Generator Welds - Energy Harbor Nuclear Corp., Davis-Besse Nuclear Power Station, Unit No. 1 ML21203A3252021-07-28028 July 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000346/2021011 ML21155A1952021-06-0404 June 2021 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Davis Besse Nuclear Power Station ML21041A5452021-02-10010 February 2021 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding Steam Generator Tube Inspection Reports ML21007A3732021-01-0707 January 2021 NRR E-mail Capture - (External_Sender) (External) Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, ML21004A1442020-12-30030 December 2020 NRR E-mail Capture - Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff ML20300A5592020-10-27027 October 2020 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML20154K7642020-06-0202 June 2020 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425 ML20133J9792020-05-14014 May 2020 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML20127H8672020-05-0606 May 2020 NRR E-mail Capture - Beaver Valley, Davis-Besse, and Perry - Request for Additional Information Regarding Request for Exemptions from Part 73 Security Requalification Requirements ML20021A3162020-01-21021 January 2020 NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request to Revise Containment Leakage Rate Testing ML19192A2222019-07-18018 July 2019 Request for Additional Information Regarding Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML19179A1382019-06-28028 June 2019 NRR E-mail Capture - Davis-Besse - Request for Additional Information Regarding the Decommissioning Quality Assurance Program ML19164A1532019-06-13013 June 2019 NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request for Post-Shutdown Emergency Plan ML19162A3922019-06-11011 June 2019 NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications ML19143A0732019-05-29029 May 2019 FENOC Fleet - Beaver Valley, Units 1 and 2; Davis-Besse, Unit 1, Perry, Unit 1 - Supplemental Information Needed for Acceptance of Requested Licensing Action; Application for Order Consenting to License Transfer and Conforming Amendments ML18305B0192018-11-0101 November 2018 18 Davis-Besse Nuclear Power Station - Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information(Rdb) ML18201A4122018-07-19019 July 2018 NRR E-mail Capture - Davis-Besse - Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805 ML18190A4902018-07-0909 July 2018 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team), Inspection Report 05000346/2018011 (DRP-DXB) ML18102B0852018-04-12012 April 2018 NRR E-mail Capture - Follow-up Request for Additional Information (RAI) FENOC FLEET-- Exemption Request for a Physical Barrier Requirement for Beaver ML18043A0102018-02-0909 February 2018 NRR E-mail Capture - FENOC--MG0010-MG0011, MG-0012, MG0013-- Request for Additional Information (RAI) - Exemption Request Security Barrier in Physical Plans ML17355A3722017-12-21021 December 2017 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805 ML17303B1582017-11-0707 November 2017 FENOC-Beaver Valley Power Station, Units 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, Perry Nuclear Power Plant Unit 1 - Generic Letter 2016-01, Request for Supplemental Information ML17257A1402017-09-14014 September 2017 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805 ML17135A3612017-05-12012 May 2017 Information Request for NRC Triennial Evaluations of Changes, Tests, and Experiments (50.59) Baseline Inspection 05000346/2017010 (Jvb) ML17129A4112017-05-0909 May 2017 Request for Additional Information Regarding Evaluation Submitted in Response to License Renewal Commitment No. 54 ML17100A1732017-04-19019 April 2017 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Associated Standard 805 ML16364A2792017-01-23023 January 2017 Request for Additional Information Regarding License Renewal Commitment No. 42 ML16355A0352016-12-19019 December 2016 Ltr 12/19/16 Davis-Besse Nuclear Power Station, Unit 1 - Information Request for an NRC Post-Approval Site Inspection for License Renewal 05000346/2017009 (Bxj) ML16256A0662016-10-18018 October 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Associated Standard 805 ML16196A0152016-07-22022 July 2016 Request for Additional Information Regarding Amendment Request to Revise Emergency Action Level Scheme L-16-122, Completion of Required Action by NRC Order EA-12-051, Reliable Spent Fuel Pool Instrumentation2016-06-24024 June 2016 Completion of Required Action by NRC Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML16060A0122016-02-29029 February 2016 FENOC - Email RAI to Licensee Regarding LAR for Changes to TS 5.3.1 CAC Nos. MF7118, MF7119, and MF7120 ML16047A1452016-02-22022 February 2016 Supplemental Information Needed for Acceptance of License Amendment Request to Adopt National Fire Protection Associated Standard 805 ML16019A3972016-01-20020 January 2016 Request for Additional Information Related to Amendment Request for Emergency Diesel Generator Minimum Voltage Surveillance Requirements ML15222A1792015-09-21021 September 2015 Request for Additional Information Related to Amendment Request for Emergency Diesel Generator Minimum Voltage Surveillance Requirements (TAC No. MF6060)(L-15-117) 2023-07-13
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 18, 2011 Barry S. Allen Vice President, Davis-Besse Nuclear Power Station FirstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor, OH 43449
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION - SECTION 2.2 & 2.3 (TAC NO. ME4640)
Dear Mr. Allen:
By letter dated August 27,2010, FirstEnergy Nuclear Operating Company, submitted an application pursuant to Title 10 of the Code of Federal Regulation Part 54 (10 CFR Part 54) for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." During its review, the staff has identified areas where additional information is needed to complete the review .. The staff's requests for additional information are included in the Enclosure. Further requests for additional information may be issued in the future.
Items in the enclosure were discussed with Cliff Custer, of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions.
please contact me by telephone at 301-415-2277 or bye-mail at brian.harris2@nrc.gov.
Sincerely,
//./ ~.~<~~tl*
/........... . .
Brian K. Harris, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION REVIEW 2.2 PLANT-LEVEL SCOPING RESULTS RAI2.2-1 License renewal application (LRA) Section 2.2, Tables 2.2-1, Table 2.2-2 and Table 2.2-3 provide the results of applying the license renewal scoping criteria to the systems, structures, and commodities. The license renewal scoping criteria was described in Section 2.1. The following updated safety analysis report (USAR) systems could not be located in LRA Tables 2.2-1 or 2.2-2.
USAR Section System 5.2.6 Loose Parts Monitoring Loose Parts Monitoring System 9.2.4.2 System Description Domestic Water System 10.4.8 Steam Generator Slow Down System Steam Generator Slowdown System 11.5 Solid Waste System Solid Waste System 9.1.4. Fuel Handling System Fuel Handling System The staff requests that the applicant justify its exclusion of the above systems in Tables 2.2-1, 2.2-2 or 2.2-3.
2.3 SCOPING AND SCREENING RESULTS: MECHANICAL SYSTEMS RAI2.3-01 LRA Section 2.1 describes the applicant's scoping methodology, which specifies how systems or components were determined to be included in scope of license renewal. The staff confirms the inclusion of all components subject to an aging management review (AMR) by reviewing the results of the screening of components within the license renewal boundary.
For the drawing locations identified in the table below, the continuation of piping in scope for license renewal could not be found.
License Renewal Application Continuation Issue i (LRA)Section I Drawing Number I
& Location
- 2.3.3.3 Auxiliary Steam and Station Heating System I LR-M021, Rev 1, F-14 & G-14 Valves SH528 & SH537 continuation drawings were not provided.
! LR-M021, Rev 1, F-13 & G-13 Valves SH331 & SH332 continuation drawings were not provided. I
~R-M021, Rev 1, F-12 & G-12 Valves SH30 & SH31 continuation drawings were not ENCLOSURE
-2 provided.
LR-M021, Rev 1, F-11 & G-11 Valves SH544 & SH520 continuation drawings were not provided.
LR-M021, Rev 1, F-9 Valves SH156 & SH157 continuation drawings were not provided.
LR-M021, Rev 1, F-8 Valves SH175 & SH176 continuation drawings were not provided.
2.3.3.11 Demineralized Water Storage System LR-M010C Rev. 0, K-10 and K-11 Continuation of 1"-HCO-37 overflow piping and 1"HCO 38 piping is not provided.
2.3.3.19 Makeup Water Treatment System Drawing LR-M011, Rev 0, A-8, 8-7 LR Note 1 and Note 7 indicate Station Plumbing and E-6 continues on drawings M-160, M-161 and M-192. These continuation drawings were not provided.
2.3.3.30 Station Blackout Diesel Generator System LR-M0170 Rev. 0, H-8 Continuation to the governor air booster pump is not provided.
2.3.3.31 Station Plumbing, Drains, and Sumps System M-041C, G-3, 7 & 10 Continuation of 4"-MSO-3 to containment normal sump is not provided.
2.3.4.1 Auxiliary Feedwater System LR-M0060, Rev 0, G-10 Valve AF2659 continuation drawings are not provided.
LR-M0060, Rev 0,G-12 Valves AF416A & AF4168 continuation drawings were not provided.
LR-M0060, Rev 0,H-12 Valves AF498A & AF4988 continuation drawings were not provided.
2.3.4.3 Main Feedwater System LR-M-0060, Rev 0, C-2 & G-4 Valves FW5885A & FW500A continuation drawings were not provided.
2.3.4.4 Main Steam System LR-M003A, Rev 0,8-2 & E-3 Valves IA566 & IA562 continuation drawings were not provided.
LR-M003A, Rev 0,0-7 & F-7 Valves MS210A & MS209A continuation drawings were not provided.
LR-M003C, Rev 1, E-11 & F-11 Valves MS2063 (MS2067) & MS2062 (MS2066) continuation drawings were not provided.
LR-M003C, Rev 1, H-5 & H-7 Valves MS58 & MS59 continuation drawings were not provided.
LR-M003C, Rev 1, K-5 Valves MS53 & MS54 continuation drawings were not provided.
LR-M003C, Rev 1, K-9 Valves MS51 & MS52 continuation drawings were not provided.
LR-M007A, Rev 0,0-6 & 0-9 Valves ICS11A8 & IS811 88 continuation drawings were not provided.
LR-M0078, Rev 1, 0-2 & 0-9 Valves IA 1008E & IA 1009E continuation drawings were not provided.
- 3 LR-M0078, Rev 1, 8-3 & 8-12 Valves FW26858, FW2685D, FW26868 & FW2686D continuation drawings were not provided.
I LR-M0078, Rev 1, 8-5 & 8-11 Valves AF6456A, AF64568, AF6457 A & AF64578 continuation drawings were not provided.
The staff requests the applicant to provide sufficient information to locate the license renewal boundary. If the continuation cannot be shown on license renewal boundary drawings, then provide additional information describing the extent of the scoping boundary and verify whether or not there are additional AMR component types between the continuation and the termination of the scoping boundary. If the scoping classification of a section of the piping changes over the continuation, provide additional information to clarify the change in scoping classification.
2.3.3 AUXILIARY SYSTEMS 2.3.3.4 Boron Recovery System RAI 2.3.3.4-01 LRA Section 2.1 describes the applicant's scoping methodology, which specifies how systems or components were determined to be included in scope of license renewal. The staff confirms the inclusion of all components subject to an AMR by reviewing the results of the screening of components within the license renewal boundary.
License renewal drawing LR-M0338, Rev 0, location G-8 shows a section of 10 CFR 54.4 (a)(2) piping (1"-HSC-18) continuing from drawing LR-M037D, location C-5 (from the Sodium Hydroxide Mix Tank) where it is not included in scope of license renewal.
The staff requests the applicant to provide additional information to clarify the scoping classification of this pipe section.
2.3.3.11 Demineralized Water Storage System RAI 2.3.3.11-01 In LRA Section 2.1 the applicant states that its screening process was used to identify the passive, long-lived structures and components in the scope of license renewal and subject to an AMR. The staff confirms inclusion of all components subject to an AMR by reviewing component types within the license renewal boundary.
License renewal drawing LR-M010C Rev. 0, location K-11, shows a fluid level gage component that provides a pressure boundary function. This component type was not included in LRA Table 2.3.3-11, "Demineralized Water Storage System Components Subject to Aging Management Review."
The staff requests the applicant to justify the exclusion of the fluid level gage component type from LRA Table 2.3.3-11.
2.3.3.12 Emergency Diesel Generators System
-4 RAI 2.3.3.12-01 In LRA Section 2.1, the applicant states that its screening process was used to identify the passive, long-lived structures and components in the scope of license renewal and subject to an AMR. The staff confirms inclusion of all components subject to an AMR by reviewing component types within the license renewal boundary.
Drawings LR-OS041 A 1, location G-3, and LR-OS041 A2, locations G-21, show sight glass components as in scope for license renewal. At locations G-7 and G-25 on the same drawings, flow glass components are shown as in scope for license renewal. The sight glass and flow glass components perform a pressure boundary function but were not included in LRA Table 2.3.3-12, "Emergency Diesel Generator System Components Subject to Aging Management Review."
The staff requests the applicant to justify the exclusion of the sight glass and flow glass components from LRA Table 2.3.3-12.
2.3.3.18 Makeup and Purification System RAI 2.3.3.18-01 LRA Section 2.1 describes the applicant's scoping methodology, which specifies how systems or components were determined to be included in scope of license renewal. The staff confirms the inclusion of all components subject to an AMR by reviewing the results of the screening of components within the license renewal boundary.
License. renewal drawing LR-M031C, Rev 0, location 0-13, shows 10 CFR 54.4(a)(2) line 1W' HSC-61 continuing to drawing LR-M040A, location E-8, where it is shown as not in scope.
The staff requests the applicant to provide additional information to clarify the scoping classification of this pipe section.
2.3.3.19 Makeup Water Treatment System RAI 2.3.3.19-01 LRA Section 2.1 describes the applicant's scoping methodology, which specifies how systems or components were determined to be included in scope of license renewal. The staff confirms the inclusion of all components subject to an AMR by reviewing the results of the screening of components within the license renewal boundary.
License renewal drawing LR-M011, Rev 0, location C-7, shows a 6"-JEE line in scope for 10 CFR 54.4(a)(2). The license renewal boundary is shown to end at valve DM65 without an explanation for the scoping change. If the piping and components downstream of this point have not left a space containing components in scope for 10 CFR54.4(a)(1) then the scoping boundary for spatial interaction should not end.
The staff requests the applicant to justify its exclusion of the the piping and components upstream of valve DM65 from the scope of license renewal.
2.3.3.21 Miscellaneous Liquid Radwaste System
-5 RAI 2.3.3.21-01 LRA Section 2.1 describes the applicant's scoping methodology, which specifies how systems or components were determined to be included in scope of license renewal. The staff confirms the inclusion of all components subject to an AMR by reviewing the results of the screening of components within the license renewal boundary.
Drawing LR-M039A, Rev 1, location E-8, provides LR Note 8 which states "Components beyond the highlighting are in the Condensate Demineralizer system and are not within the scope of license renewal." The staff questions if the piping and components downstream of this point occupy a space containing components in scope for 10 CFR 50.4(a)(1) and therefore, would be required to be in scope for spatial interaction.
The staff requests the applicant to justify its exclusion of the components downstream of LR Note 8 from scope of license renewal.
RAI 2.3.3.21-02 LRA Section 2.1 describes the applicant's scoping methodology, which specifies how systems or components were determined to be included in scope of license renewal. The staff confirms the inclusion of all components subject to an AIVIR by reviewing the results of the screening of components within the license renewal boundary.
Drawing LR-M0398, Rev 1, location E-3, downstream of valve WM142 provides LR Note 8 which states "Components beyond the highlighting are not in the scope of license renewaL" The staff questions if these components occupy a space containing components in scope for 10 CFR 50.4(a)(1) and would therefore be required to be in scope for spatial interaction.
The staff requests the applicant to justify its exclusion of the components downstream of valve WM142 from scope of license renewal.
RAI 2.3.3.21-03 LRA Section 2.1 describes the applicant's scoping methodology, which specifies how systems or components were determined to be included in scope of license renewal. The staff confirms the inclusion of all components subject to an AMR by reviewing the results of the screening of components within the license renewal boundary.
Drawing LR-M037C, Rev 0, location K-12, shows 1 W'-HSC-109 continued from drawing LR M037D as in scope. However, drawing LR-M037D, location C-1 shows this piping as not in scope.
The staff requests the applicant to provide additional information to clarify the scoping classification of this pipe section.
-6 2.3.3.22 Nitrogen Gas System RAI 2.3.3.22-01 LRA Section 2.1 describes the applicant's scoping methodology, which specifies how systems or components were determined to be included in scope of license renewal. The staff confirms the inclusion of all components subject to an AMR by reviewing the results of the screening of components within the license renewal boundary .
. License renewal drawing LR-M019, Rev 0, locations E/F-14, and K-1, show electrical penetrations PIC 5SX, PIL 5WX and P2L 2CX as not in scope for license renewal. However similar electrical penetrations at locations A thru D-14 and E thru F-1 are shown as in scope for license renewal to the upstream check valve.
The staff requests the applicant to justify its exclusion of electrical penetrations PIC 5SX, PIL 5WX and P2L 2CX from the scope of license renewal.
2.3.3.25 Sampling System RAI 2.3.3.25-01 LRA Section 2.1 describes the applicant's scoping methodology, which specifies how systems or components were determined to be included in scope of license renewal. The staff confirms the inclusion of all components subject to an AMR by reviewing the results of the screening of components within the license renewal boundary.
License renewal drawing LR-M-042C, location E-2, shows line %" -HCC-112 continuing from drawing M-031 C, location C-4 as in scope for license renewal; however the same line is shown as not in scope on drawing LR-M-031C.
The staff requests the applicant to provide additional information to clarify the scoping classification of this pipe section.
RAI 2.3.3.25-02 LRA Section 2.1 describes the applicant's scoping methodology, which specifies how systems or components were determined to be included in scope of license renewal. The staff confirms the inclusion of all components subject to an AMR by reviewing the results of the screening of components within the license renewal boundary.
License renewal drawing LR-M-042B, Rev 0, location E-8, shows a sample line (sample No. S 039-6) as not in scope for license renewal. However, on drawing LR-M039B this sample line is shown as in scope for license renewal starting at location H-7 and returning at location E-4.
The staff requests the applicant to provide additional information to clarify the scoping classification of this pipe section.
-7 2.3.3.26 Service Water System RAI 2.3.3.26-01 LRA Section 2.1 describes the applicant's scoping methodology, which specifies how systems or components were determined to be included in scope of license renewal. The staff confirms the inclusion of all components subject to an AMR by reviewing the results of the screening of components within the license renewal boundary.
On drawing LR-M041A, Rev. 0, location K-5, the continuation of 3/8" HBD piping from Dilution Pump P180 is shown in scope for license renewal. Contrary to the information in bullet 3 on Page 2.3-129 of the LRA, the 3/8" HBD piping is not shown as a rubber hose on drawing LR M041A.
The staff requests the applicant to provide clarification as to whether the 3/8" HBD line is pipe or rubber hose.
2.3.3.30 Station Blackout Diesel Generator System RAI 2.3.3.30-01 In LRA Section 2.1, the applicant states that its screening process was used to identify the passive, long-lived structures and components in the scope of license renewal and subject to an AMR. The staff confirms inclusion of all components subject to an AIVIR by reviewing component types within the license renewal boundary.
The applicant depicts on LRA drawing LR-M017D, Rev.O, location G-4 and J-4 an air dryer housing and at location E-10 an air intake vibration damper housing in scope of license renewal.
However, the air dryer and vibration damper housings were not included in LRA Table 2.3.3-30.
The staff requests the applicant to justify the exclusion of these housing components from LRA Table 2.3.3-30, "Station Blackout Diesel Generator System Components Subject to Aging Management Review."
RAI 2.3.3.30-02 In LRA Section 2.3.3.30 in the SBODG Jacket Water System on page 2.3-139 there is a discussion in paragraph four about two fans which start automatically to cool the radiator cooling coils when needed. The applicant stated "If the fans are out of service, and the SBODG must be run, most of the cooling can be provided by spraying water on the radiator coils. Engine load capacity in this case will have to be limited to prevent engine overheating depending on weather conditions. "
The spray system components for spraying water on the radiator coils are not identified in the LRA or in Chapter 8 of the USAR. It is not clear if these components are required to be in scope for license renewal.
The staff requests the applicant provide a description for the method for spraying down the radiator coils and clarify if the necessary components are in scope for license renewal.
- 8 RAI 2.3.3.30-03 In LRA Section 2.1, the applicant states that its screening process was used to identify the passive, long-lived structures and components in the scope of license renewal and subject to AMR. The staff confirms inclusion of all components subject to an AMR by reviewing component types within the license renewal boundary.
On drawing LR-M017D, Rev. 0, location H-4 and K-4 there are check valves DA205 and D0204 respectively that are needed to maintain pressure in the air receiver tanks for the SBODG Air Start System. The 1-inch pipelines currently end the scoping boundary at manually operated, normally open ball valves DA207 and DA206 while check valves DA205 and DA204 are not included within the boundary. The check valves typically function to maintain air pressure in the air receiver tank. An example of check valves in scope on similar air receiver tanks is shown on LRA drawing LR-M017B, Rev. 0 at locations C-5, E-6, G-6 and J-5.
The staff requests the applicant to provide an explanation why the license renewal boundaries do not extend to the DA205 and DA204 check valves.
2.3.4 STEAM AND POWER CONVERSION SYSTEMS 2.3.4.1 Auxiliary Feedwater System RAI 2.3.4.1-01 In LRA Section 2.1, the applicant states that its screening process was used to identify the passive, long-lived structures and components in the scope of license renewal and subject to an AMR. The staff confirms inclusion of all components subject to an AIVIR by reviewing component types within the license renewal boundary.
Drawing LR-M006D, Rev. 0, location H-9, shows piping (6"-HBD-137) that is in scope for 10 CFR 54.4(a}(2) as non-safety piping attached to safety related piping. The scoping boundary ends at the limit of the Seismic Analysis (S/I flag), but it is not clear if the piping downstream of this point is still within the same space as the safety related components. The staff questions if this pipe line downstream of the SII interface is fluid filled and located in the vicinity of 10 CFR 54.4(a)(1) components.
The staff requests the applicant to provide sufficient information to verify that the not in scope piping is not located in an area with 10 CFR 54.4(a)(1) components.
2.3.4.3 Main Feedwater System RAI 2.3.4.3-01 In LRA Section 2.1, the applicant states that its screening process was used to identify the passive, long-lived structures and components in the scope of license renewal and subject to an AMR. The staff confirms inclusion of all components subject to an AMR by reviewing component types within the license renewal boundary.
The applicant depicts on drawing LR-M006D, Rev 0, locations H-2, and C-14, drip rim drains below the Motor Driven Start-up Feed Pump 1-1, and Aux. Feed Pumps P14-1 and P14-2 as not in of scope. These drains may contain fluid and are apparently in an area that contains
-9 safety related components, in which case they would be included within the scope of license renewal under 10 CFR 54.4(a)(2).
The staff requests the applicant to provide additional information to explain why the drip rim drain and connected piping are not in scope.
2.3.4.4 Main Steam System RAI 2.3.4.4-01 In LRA Section 2.1, the applicant states that its screening process was used to identify the passive, long-lived structures and components in the scope of license renewal and subject to an AMR. The staff confirms inclusion of all components subject to an AIVIR by reviewing component types within the license renewal boundary.
The applicant depicts on drawing LR-M045, Rev 1, locations 0-12 and 0-14, piping to valves SC200 and SC201 from the to Steam Generator Wet Lay-Up Chemical Addition Tanks as not in scope. However, these tanks as well as additional piping lines connected to the tanks are shown as in scope for 10 CFR 54.4(a)(2).
The staff requests the applicant to justify its exclusion of the %" piping to valves SC200 and SC201 from the scope of license renewal.
RAI 2.3.4.4-02 In LRA Section 2.1, the applicant states that its screening process was used to identify the passive, long-lived structures and components in the scope of license renewal and subject to an AMR. The staff confirms inclusion of all components subject to an AMR by reviewing component types within the license renewal boundary.
Drawing LR-M-045, Rev 1, locations E-11 and E-13, shows anti-siphon devices downstream of the Steam Generator Wet Lay-Up Chemical Addition Metering Pumps 1-1 and 1-2 as not in scope. The piping to which these components are attached is in scope for 10 CFR 54.4(a)(2).
The staff requests the applicant to provide additional information to explain why the anti-siphon device is not in scope and not listed as a component type in LRA Table 2.3.4-4, "Main Steam System Components Subject to Aging Management Review."
ML110700732 OFFICE: LR PM:RPB1 :DLR BC:RPB1 :DLR PM:RPB1 :DLR NAME: IKing Harris BPham BHarris DATE: 3/16/11 117111 3/18/11 3/18/11 Letter to B. Allen from B. Harris Dated March 18, 2011
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION - SECTION 2.2 & 2.3 (TAC NO. ME4640)
HARDCOPY:
DLR RF E-MAIL:
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