Letter Sequence Other |
---|
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:Audit Report
MONTHYEARML16134A6952016-05-24024 May 2016 NRC Report for the Audit of Firstenergy Nuclear Operating Company'S Flood Hazard Reevaluation Report Submittal Related to the Near-Term Task Force Recommendation 2.1-Flooding for: Davis Besse Nuclear Power Station, Unit 1 ML16019A3672016-02-0808 February 2016 Report for the Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML13295A5182014-12-11011 December 2014 Audit of the Licensee'S Management of Regulatory Commitments (MF2803) ML14007A6702014-02-21021 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML11122A0142011-06-0101 June 2011 Audit Report Regarding the Davis-Besse Nuclear Power Station License Renewal Application ML1110500912011-04-19019 April 2011 Scoping and Screening Audit Report Regarding the Davis-Besse Nuclear Power Station License Renewal Application ML1100605982011-01-20020 January 2011 Correction of Audit of the Licensee'S Management of Regulatory Commitments ML1036204732010-12-29029 December 2010 Audit of the Licensee'S Management of Regulatory Commitments ML1011701962010-05-19019 May 2010 Audit of Steam Generator Program Focusing on Steam Generator Tube Integrity During a Large Break Loss of Coolant Accident ML0627004762007-03-0202 March 2007 Audit of the Licensee'S Management of Regulatory Commitments ML0530701702000-07-0707 July 2000 12 RFO QA Audit, Toledo Edison Quality Assessment Audit AR-00-OUTAG-01 ML0530703781990-02-0808 February 1990 Generic Letter 88-05: Prevention of Boric Acid Corrosion at Davis-Besse Nuclear Power Plant 2016-05-24
[Table view] 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] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 19, 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:
SCOPING AND SCREENING AUDIT REPORT REGARDING THE DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION (TAC NO. ME4640)
Dear Mr. Allen:
By letter dated August 27, 2010, FirstEnergy Nuclear Operating Company, submitted an application pursuant to 10 Code of Federal Regulation Part 54 for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station. On January 28, 2011, the staff of the U.S.
Nuclear Regulatory Commission completed the on-site audit of aging management programs.
The audit report is enclosed.
If you have any questions, please contact me by telephone at 301-415-2277 or bye-mail at brian. harris2@nrc.gov.
Sincerely, 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: Listserv
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION, DIVISION OF LICENSE RENEWAL Docket No: 050-00346 License No: NPF-3 Licensee: FirstEnergy Nuclear Operating Company Facility: Davis-Besse Nuclear Power Station Location: 5501 North State Route 2 Oak Harbor, OH 43449 Dates: January 24 - 28, 2011 Reviewers: B. Rogers, Reactor Engineer, Division of License Renewal (DLR)
S. Sakai, Mechanical Engineer, DLR A. Buford, Structural Engineer, DLR M. Homiack, Mechanical Engineer, DLR D. Brittner, Mechanical Engineer, DLR E. Smith, Reactor Engineer, Division of Safety Systems (DSS)
E. Davidson, Reactor Engineer, DSS L Howard, Consultant, Southwest Research Institute (SWRI)
R. Brient, Consultant, SWRI J. Nickolaus, Consultant, Pacific Northwest National Laboratory ENCLOSURE
SCOPING AND SCREENING AUDIT REPORT REGARDING THE DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION I. Introduction During the week of January 24 - 28, 2011, the Division of License Renewal, Aging Management of Structures, Electrical and Systems Branch, performed an audit of the FirstEnergy Nuclear Operating Company (FENOC or the applicant) license renewal scoping and screening methodology developed to support the license renewal application (LRA) for Davis-Besse Nuclear Power Station, Unit 1 (Davis-Besse). The audit was performed at the applicant's facility located on the southwestern shore of Lake Erie in Ottawa County in northwestern Ohio. The focus of the staff's audit was the applicant's administrative controls governing implementation of the LRA scoping and screening methodology and review of the technical basis for selected scoping and screening results for various plant systems, structures, and components (SSCs).
The audit team also reviewed quality attributes for aging management programs (AMPs), quality practices used by the applicant to develop the LRA, and training of personnel that developed the LRA.
The regulatory bases for the audit were Title 10 of the Code of Federal Regulations, Part 54, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants," (10 CFR Part 54) and NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants," Revision 2 (SRP-LR). In addition, the applicant developed the LRA in accordance with Nuclear Energy Institute (NEI) 95-10, "Industry Guidelines for Implementing the Requirements of 10 CFR 54 - The License Renewal Rule," Revision 6 (NEI 95-10) which the NRC has endorsed via Regulatory Guide 1.188, "Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses," (Regulatory Guide 1.188).
II. Background 10 CFR 54.21, "Contents of Application - Technical Information," requires that each application for license renewal contain an integrated plant assessment (IPA). Furthermore, the IPA must list and identify those structures and components (SCs) subject to an aging management review (AMR) from the SSCs that are included within the scope of license renewal. 10 CFR 54.4(a) identifies the plant SSCs within the scope of license renewal. SCs within the scope of license renewal are evaluated to determine if they are long-lived and passive equipment and, therefore, subject to an AMR in accordance with 10 CFR 54.21 (a)(1).
III. Scoping Methodology The scoping evaluations for the Davis-Besse LRA were performed by the applicant's license renewal project personnel. The audit team conducted detailed discussions with the applicant's license renewal project personnel and reviewed documentation pertinent to the scoping process. The audit team assessed whether the scoping methodology outlined in the LRA and implementation procedures were appropriately implemented and whether the scoping results were consistent with current licensing basis requirements.
The audit team conducted a review of a sample of 85 components from the applicant's configuration database to verify that the selected components were correctly identified as being within the scope of license renewal. The audit team reviewed the selected components, which
2 included mechanical, electrical and structural components, using the applicant's documents including the Updated Safety Analysis Report (USAR), system information and piping and instrumentation drawings to perform its review.
The audit team also reviewed a sample of system scoping results for the following systems and structures: service water, emergency diesel generators and support systems, main feedwater, auxiliary feedwater, and the turbine building. The audit team determined that the applicant's scoping methodology was generally consistent with the requirements of the Rule for the identification of SSCs that meet the scoping criteria of 10 CFR 54.4(a). However, the audit team determined that additional information was required in order for the staff to complete its review:
- The applicant identified nonsafety-related structures, systems, and components (SSCs) in the vicinity of the safety-related components located in the turbine building. The applicant had concluded that the nonsafety-related SSCs were not required to be included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).
The staff requested that the applicant provide a description and the results of the evaluation that formed the basis for the conclusion that the nonsafety-related SSCs do not meet the criteria for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2) for spatial interaction.
- The staff determined that the applicant did not include nonsafety-related relief valve drain lines, within the vicinity of safety-related SSCs, within the scope of license renewal. The staff requested that the applicant provide a description and the results of the evaluation that formed the basis for the conclusion that the nonsafety-related SSCs do not meet the criteria for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2) for spatial interaction.
- The staff determined that the applicant did not include nonsafety-related drip pans and retention area drain lines, within the vicinity of safety-related SSCs, within the scope of license renewal. The staff requested that the applicant provide a description and the results of the evaluation that formed the basis for the conclusion that the nonsafety related SSCs do not meet the criteria for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2) for spatial interaction.
- During a plant walkdown, the staff observed a nonsafety-related domestic water valve and other nonsafety-related fluid filled SSCs located in the service water tunnel and in the vicinity of safety-related SSCs. The staff requested that the applicant provide a description and the results of the evaluation that formed the basis for the conclusion that the nonsafety-related SSCs do not meet the criteria for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2) for spatial interaction.
- The staff determined through a review of license renewal drawings and discussion with the applicant that for certain systems nonsafety-related pipe attached to safety-related pipe had not been included within the scope of license renewal. The staff requested that the applicant provide details of the analysis performed and any conclusions related to nonsafety-related pipe, attached to safety-related pipe, for inclusion within the scope
3 of license renewal up to and including a seismic anchor or equivalent, in accordance with 10 CFR 54.4(a)(2).
- The staff determined through a review of license renewal drawings and discussion with the applicant that equipment that was no longer required had been placed in an abandoned state. The staff requested that the applicant provide details on the activities performed to confirm that all abandoned equipment that at any time contained fluids, and is in the proximity of safety-related SSCs, has been verified to be drained. If abandoned equipment had not been verified to be drained or is not included within the scope of license renewal, provide details of the analysis performed and any conclusions, related to the inclusion of abandoned equipment within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).
- During a plant walkdown, the staff observed the nonsafety-related condensate line located in the turbine building that exited through the deck to the space below that contained the auxiliary feedwater pumps. The applicant indicated that the condensate line nonsafety-related to safety-related interface was located at a point below the turbine building deck. The staff requested that the applicant identify the specific location of the nonsafety to safety-related interface and all mitigative features installed to protect the integrity of the nonsafety to safety-related interface. The staff requested that the applicant provide the evaluation of all components and structures relied upon to protect the safety/nonsafety interface for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).
- The staff determined through a review of the service water aging management review documentation that the service water pump bolts were excluded from the scope of license renewal based on periodic replacement. However, the aging management review documentation indicated that a visual inspection was also used to determine whether bolt replacement would be required. The staff determined that the use of inspection activities to determine the need to replace a component did not meet the requirements of 10 CFR 54.21 (a)(1 )(ii) - replacement based on a qualified life or specified time period. The staff requested that the applicant provide details of the analysis performed and any conclusions, related to the review of service water pump bolts, for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).
IV. Screening Methodology The audit team reviewed the methodology used by the applicant to determine if mechanical, structural, and electrical components within the scope of license renewal would be subject to an AMR (screening). The applicant provided the audit team with a detailed discussion of the processes used for each diSCipline and provided administrative documentation that described the screening methodology. The audit team also reviewed the screening results reports for the service water, emergency diesel generators and support systems, main feedwater, auxiliary feedwater, and the turbine building. The audit team noted that the applicant's screening process was performed in accordance with its written requirements and was consistent with the guidance provided in the SRP-LR and NEI 95-10. The audit team determined that the
4 screening methodology was consistent with the requirements of the Rule for the identification of SSCs that meet the screening criteria of 10 CFR 54.21(a)(1).
V. Aging Management Program Quality Assurance Attributes The audit team reviewed the applicant's AMPs described in Appendix A, "Updated Safety Analysis Report Supplement," and Appendix B, "Aging Management Programs," of the Davis Besse LRA for inclusion of the appropriate quality assurance (QA) requirements for elements NO.7 (corrective action), NO.8 (confirmation process), and NO.9 (administrative controls). In addition, the audit team reviewed AMP basis documents to ensure consistency in the use of the QA attributes for each program. The purpose of this review was to ensure that the aging management activities were consistent with the staff's guidance described in SRP-LR, Section A.2, "Quality Assurance for Aging Management Programs (Branch Technical Position IQMB-1)."
Based on the audit team's evaluation, the descriptions and applicability of the AMPs and their associated quality attributes, provided in Appendix A, Section A.1, "Summary Descriptions of Aging Management Programs and Activities," and Appendix B, Section B.1.3, "Quality Assurance Program and Administrative Controls," of the LRA, were determined to be generally consistent with the staff's position regarding QA for aging management.
VI. Quality Assurance Controls Applied to LRA Development The staff reviewed the quality controls used by the applicant to ensure that scoping and screening methodologies used to develop the LRA were adequately implemented. The applicant used the following quality control processes during the LRA development:
- The applicant developed written procedures to direct implementation of the scoping and screening methodology, to control LRA development, and to describe training requirements and documentation.
- The applicant's reviews of the LRA included management and technical reviews, industry peer review and sufficiency check, and licensing reviews by Fleet Licensing, Corporate Legal, the Plant Operations Review Committee, and the Corporate Nuclear Review Board for License Amendment Requests.
- The LRA submittal review and approval was performed by the License Renewal Project Manager, Davis-Besse Senior Leadership Team, and Fleet Licensing Manager.
- The comments received throughout the review process were addressed. The audit team reviewed a sample of comment resolution documentation and determined that the applicant's comment resolution process is consistent and adequate.
- The applicant used its open item tracking system to capture any identified issues for resolution.
5 The audit team performed a sample review of reports and LRA development procedures, the applicant's documentation of the activities performed to assess the quality of the LRA, and held discussions with the applicant's license renewal personnel. The audit team determined that the applicant's activities provide assurance that LRA development activities were performed consistently with the applicant's license renewal program requirements.
VII. Training for License Renewal Project Personnel The audit team reviewed the applicant's training process to ensure the guidelines and methodology for the scoping and screening activities were applied in a consistent and appropriate manner. The applicant required training for personnel participating in the development of the LRA and used only trained and qualified personnel to prepare the scoping and screening implementing procedures and reports.
- Training was required for the license renewal project personnel, which followed documented procedures.
- Initial orientation training/overview was provided to license renewal personnel for familiarization with U.S. Nuclear Regulatory Commission (NRC) regulations and industry guidance.
- The training for project personnel included required reading and general review.
On the basis of discussions with the applicant's license renewal personnel responsible for the scoping and screening process, and a review of selected documentation in support of the process, the NRC audit team determined that the applicant's personnel understood the requirements and adequately implemented the scoping and screening methodology established in the applicant's renewal application.
VIII. Final Briefing A final briefing was held with the applicant on January 28, 2011, to discuss the results of the scoping and screening methodology audit. The audit team identified preliminary areas where additional information would be required to support completion of the staffs LRA review.
IX. Documents Reviewed
- 1. NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants," Revision 2
- 2. NEI 95-10, "Industry Guideline for Implementing the Requirements of 10 CFR Part 54 The License Renewal Rule," Revision 6
6
- 3. LRPI-01, Davis-Besse License Renewal Project Execution Plan - AREVA Scope
- 4. LRPI-02, System and Structure Scoping S. LRPI-03, Mechanical Screening and Aging Management Review
- 6. LRPI-04, Electrical Screening and Aging Management Review
- 7. LRPI-OS, Structural Screening and Aging Management Review
- 8. LRPI-07, TLAA and Exemption Evaluations
- 9. LRPI-09, License Renewal Open Item Tracking System
- 10. LRPI-10, License Renewal Application Development and Maintenance
- 11. LRPD-01, System and Structure Scoping Results
- 12. LRPD-OS, Aging Management Program Evaluation Results, with Attachments
- 13. LRAMR-S01, Structures Screening and Aging Management Review for the Intake Structure
- 14. LRAMR-S03, Structures Screening and Aging Management Review for the Containment 1S. LRAMR-S04, Structures Screening and Aging Management Review for Other Structures
- 16. LRAMR-S06, Structures Screening and Aging Management Review of Bulk Commodities
- 17. LRAMR-E01, Screening and Aging Management Review for Electrical Component Commodity Groups
- 18. NOP-SS-3001, Procedure Review and Approval
- 19. NOP-LP-2001, Corrective Action Program
- 20. NOBP-LP-2018, Integrated Performance Assessment and Trending
- 21. NOBP-LP-2008, FENOC Corrective Action Review Board
- 22. NOBP-LP-2007, Condition Report Process Effectiveness Review
- 23. NOBP-LP-2011, FENOC Cause Analysis
- 24. DBBP-LRP-001, License Renewal Application Review, Approval, and Maintenance
April 19, 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:
SCOPING AND SCREENING AUDIT REPORT REGARDING THE DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION (TAC NO. ME4640)
Dear Mr. Allen:
By letter dated August 27,2010, FirstEnergy Nuclear Operating Company, submitted an application pursuant to 10 Code of Federal Regulation Part 54 for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station. On January 28,2011, the staff of the U.S.
Nuclear Regulatory Commission completed the on-site audit of aging management programs.
The audit report is enclosed.
If you have any questions, please contact me by telephone at 301-415-2277 or bye-mail at brian. harris2@nrc.gov.
Sincerely, IRA!
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: Listserv DISTRIBUTION:
ADAMS A ccesslon No. ML111050091 *concurrence bye-mail OFFICE: LA:DLR* PM:RPB1 :DLR BC:RPB1:DLR PM:RPB1 :DLR NAME: SFigueroa BHarris BPham BHarris DATE: 4/18/11 4/18/11 4/19/11 4/19111 OFFICIAL RECORD COPY
Letter to B. Allen from B. Harris Dated April 19, 2011
SUBJECT:
SCOPING AND SCREENING AUDIT REPORT REGARDING THE DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION (TAC NO. ME4640)
HARDCOPY:
DLR RF E-MAIL:
PUBLIC RidsNrrDlrResource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDIrRer1 Resource RidsNrrDIrRer2 Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDciCsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource B. Harris P. Cooper B. Harris (OGC)
M. Mahoney