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| | issue date = 10/11/2017 | | | issue date = 10/11/2017 |
| | title = Evaluations of Changes, Test, and Experiments Baseline Inspection Report 05000346/2017010 | | | title = Evaluations of Changes, Test, and Experiments Baseline Inspection Report 05000346/2017010 |
| | author name = Daley R C | | | author name = Daley R |
| | author affiliation = NRC/RGN-III/DRS/EB3 | | | author affiliation = NRC/RGN-III/DRS/EB3 |
| | addressee name = Bezilla M | | | addressee name = Bezilla M |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE RD. SUITE 210 LISLE, IL 60532-4352 October 11, 2017 Mr. Mark Bezilla Site Vice President FirstEnergy Nuclear Operating Co. | | {{#Wiki_filter:UNITED STATES ber 11, 2017 |
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| Davis-Besse Nuclear Power Station 5501 N. State Rte. 2, Mail Stop A-DB-3080 Oak Harbor, OH 43449-9760
| | ==SUBJECT:== |
| | | DAVIS-BESSE NUCLEAR POWER STATION EVALUATIONS OF CHANGES, TESTS, AND EXPERIMENTS BASELINE INSPECTION REPORT 05000346/2017010 |
| SUBJECT: DAVIS-BESSE NUCLEAR POWER STATION EVALUATIONS OF CHANGES, TESTS, AND EXPERIMENTS BASELINE INSPECTION REPORT 05000346/2017010 | |
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| ==Dear Mr. Bezilla:== | | ==Dear Mr. Bezilla:== |
| On September 22, 2017 the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, and Experiments inspection at your Davis-Besse Nuclear Power Station. The enclosed inspection report documents the inspection results which were discussed on September 22, 2017, with you and other members of your staff. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. | | On September 22, 2017 the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, and Experiments inspection at your Davis-Besse Nuclear Power Station. The enclosed inspection report documents the inspection results which were discussed on September 22, 2017, with you and other members of your staff. |
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| The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. The NRC inspectors did not identify any findings or violations of more than minor significance. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, "Public Inspections, Exemptions, Requests for Withholding." | | The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license. |
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| Sincerely,/RA/
| | The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. |
| Robert C. Daley, Chief Engineering Branch 3
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| Division of Reactor Safety Docket No. 50-346 License No. NPF-3
| | The NRC inspectors did not identify any findings or violations of more than minor significance. |
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| ===Enclosure:===
| | This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding. |
| IR 05000346/2017010 cc: Distribution via LISTSERV
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| Letter to Mark Bezilla from Robert C. Daley dated October 11, 2017
| | Sincerely, |
| | /RA/ |
| | Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-346 License No. NPF-3 |
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| SUBJECT: DAVIS-BESSE NUCLEAR POWER STATION EVALUATIONS OF CHANGES, TESTS, AND EXPERIMENTS BASELINE INSPECTION REPORT 05000346/2017010 DISTRIBUTION: Jeremy Bowen RidsNrrDorlLpl3 RidsNrrPMDavisBesse Resource RidsNrrDirsIrib Resource Cynthia Pederson
| | ===Enclosure:=== |
| | IR 05000346/2017010 |
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| James Trapp
| | REGION III== |
| | Docket No: 50-346 License No: NPF-3 Report No: 05000346/2017010 Licensee: FirstEnergy Nuclear Operating Company Facility: Davis-Besse Nuclear Power Station Location: Oak Harbor, OH Dates: September 18-22, 2017 Inspectors: J. Bozga, Senior Reactor Inspector (Lead) |
| | J. Benjamin, Senior Reactor Inspector J. Gilliam, Reactor Inspector N. Khan, Electrical Engineer (Observer) |
| | Approved by: Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Enclosure |
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| Richard Skokowski Allan Barker Carole Ariano
| | =SUMMARY= |
| | | Inspection Report 05000346/2017010; 09/18/2017-09/22/2017; Davis-Besse Nuclear Power |
| Linda Linn
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| DRPIII DRSIII ROPreports.Resource@nrc.gov
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| ADAMS Accession Number: ML17286B124 OFFICE RIII RIII NAME JBozga:cl RDaley DATE 10/5 /17 10/11/17 OFFICIAL RECORD COPY
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| Enclosure U. S. NUCLEAR REGULATORY COMMISSION REGION III Docket No: 50-346 License No: NPF-3 Report No: 05000346/2017010 Licensee: FirstEnergy Nuclear Operating Company Facility: Davis-Besse Nuclear Power Station Location: Oak Harbor, OH Dates: September 18-22, 2017 Inspectors: J. Bozga, Senior Reactor Inspector (Lead) J. Benjamin, Senior Reactor Inspector J. Gilliam, Reactor Inspector
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| N. Khan, Electrical Engineer (Observer) Approved by: Robert C. Daley, Chief Engineering Branch 3
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| Division of Reactor Safety
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| | Station; Evaluations of Changes, Tests, and Experiments. |
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| =SUMMARY=
| | This report covers a 1-week announced evaluations of changes, tests, and experiments baseline inspection. The inspection was conducted by Region III based engineering inspectors. |
| Inspection Report 05000346/2017010; 09/18/2017-09/22/2017; Davis-Besse Nuclear Power Station; Evaluations of Changes, Tests, and Experiments. This report covers a 1-week announced evaluations of changes, tests, and experiments baseline inspection. The inspection was conducted by Region III based engineering inspectors.
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| The NRC's program for overseeing the safe operati on of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 6, dated July 2016. | | The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 6, dated July 201 |
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| ===NRC-Identified=== | | ===NRC-Identified=== |
| and Self-Revealed Findings No findings were identified. | | and Self-Revealed Findings No findings were identified. |
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| === | | ===Licensee-Identified Violations=== |
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| Licensee-Identified Violations===
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| No violations were identified. | | No violations were identified. |
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| =REPORT DETAILS= | | =REPORT DETAILS= |
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| ==REACTOR SAFETY== | | ==REACTOR SAFETY== |
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| ===Cornerstone:=== | | ===Cornerstone: Initiating Events, Mitigating Systems, and Barrier Integrity=== |
| Initiating Events, Mitigating Systems, and Barrier Integrity | |
| {{a|1R17}} | | {{a|1R17}} |
| ==1R17 Evaluations of Changes, Tests, and Experiments== | | ==1R17 Evaluations of Changes, Tests, and Experiments== |
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| * the safety issue requiring the change, tests or experiment was resolved; | | * the safety issue requiring the change, tests or experiment was resolved; |
| * the licensee conclusions for evaluations of changes, tests, and experiments were correct and consistent with 10 CFR 50.59; and | | * the licensee conclusions for evaluations of changes, tests, and experiments were correct and consistent with 10 CFR 50.59; and |
| * the design and licensing basis documentation was updated to reflect the change. The inspectors used, in part, Nuclear Energy Institute 96-07, "Guidelines for 10 CFR 50.59 Implementation," Revision 1, to determine acceptability of the completed evaluations, and screenings. The Nuclear Energy Institute document was endorsed by the U.S. Nuclear Regulatory Commission in Regulatory Guide 1.187, "Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments," dated November 2000. The inspectors also consulted Part 9900 of the U.S. Nuclear Regulatory Commission Inspection Manual, "10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments." This inspection constituted 30 samples of evaluations, screenings, and/or applicability determinations as defined in Inspection Procedure 71111.17-05. | | * the design and licensing basis documentation was updated to reflect the change. |
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| | The inspectors used, in part, Nuclear Energy Institute 96-07, Guidelines for 10 CFR 50.59 Implementation, Revision 1, to determine acceptability of the completed evaluations, and screenings. The Nuclear Energy Institute document was endorsed by the U.S. Nuclear Regulatory Commission in Regulatory Guide 1.187, Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments, dated November 2000. The inspectors also consulted Part 9900 of the U.S. Nuclear Regulatory Commission Inspection Manual, 10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments. |
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| | This inspection constituted 30 samples of evaluations, screenings, and/or applicability determinations as defined in Inspection Procedure 71111.17-05. |
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| ====b. Findings==== | | ====b. Findings==== |
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| ====b. Findings==== | | ====b. Findings==== |
| No findings of significance were identified. | | No findings of significance were identified. |
| {{a|4OA6}} | | {{a|4OA6}} |
| ==4OA6 Management Meetings== | | ==4OA6 Management Meetings== |
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| ===.1 Exit Meeting Summary=== | | ===.1 Exit Meeting Summary=== |
| On September 22, 2017, the inspectors presented the inspection results to Mr. M. Bezilla, Site Vice President, and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented and did not identify any proprietary content. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff. ATTACHMENT: | | |
| | On September 22, 2017, the inspectors presented the inspection results to Mr. M. Bezilla, Site Vice President, and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented and did not identify any proprietary content. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff. |
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| | ATTACHMENT: |
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| =SUPPLEMENTAL INFORMATION= | | =SUPPLEMENTAL INFORMATION= |
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| ==KEY POINTS OF CONTACT== | | ==KEY POINTS OF CONTACT== |
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| Licensee | | Licensee |
| : [[contact::M. Bezilla]], Site Vice President | | : [[contact::M. Bezilla]], Site Vice President |
| : [[contact::G. Wolf]], Regulatory Compliance Supervisor | | : [[contact::G. Wolf]], Regulatory Compliance Supervisor |
| : [[contact::D. Blakely]], Engineering Analysis Supervisor | | : [[contact::D. Blakely]], Engineering Analysis Supervisor |
| : [[contact::J. Sturdavant]], Regulatory Compliance Specialist | | : [[contact::J. Sturdavant]], Regulatory Compliance Specialist |
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| ==LIST OF ITEMS== | | ==LIST OF ITEMS== |
| OPENED, CLOSED AND DISCUSSED Opened, Closed and | | |
| | ===OPENED, CLOSED AND DISCUSSED=== |
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| | Opened, Closed and |
| ===Discussed=== | | ===Discussed=== |
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| None LIST OF ACRONYMS USED CFR Code of Federal Regulations | | None LIST OF ACRONYMS USED CFR Code of Federal Regulations |
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| ==LIST OF DOCUMENTS REVIEWED== | | ==LIST OF DOCUMENTS REVIEWED== |
| The following is a list of documents reviewed during the inspection.
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| : Inclusion on this list does not imply that the NRC inspectors reviewed the documents in their entirety, but rather, that selected sections of portions of the documents were evaluated as part of the overall inspection effort.
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| : Inclusion of a document on this list does not imply NRC acceptance of the document or any part of it, unless this is stated in the body of the inspection report.
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| : CFR 50.59 EVALUATIONS
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| : Number Description or Title Date 13-04680 Containment Vessel Analysis 01/24/2014
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| : 13-04372 Containment Vessel Analysis 01/24/2014
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| : 13-04729 36 Inch Main Steam Line Break Rm 601/602 01/24/2014
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| : 14-03427
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| : ECP 12-0270, Replacement of the Control Rod Drive (CRD)
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| system with a Digital Contro
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| l Rod Drive Control System (DCRDCS), and
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| : ECP 15-0370, AQ Requirements for Digital
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| : CRD Replacement
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| : 2/11/2016
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| : CFR 50.59 SCREENINGS
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| : Number Description or Title Date 13-04729 36 Inch Main Steam Line Break Rooms 601/602 01/15/2014 14-03200 Battery Room Heaters 05/27/2015
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| : 14-04107 Spent Fuel Pool Cooling Malfunctions 12/08/2014
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| : 14-04284 Technical Specification for Station Blackout Diesel Generator System 12/19/2014 15-00312 Decay Heat Pump Recirculation Line Support Changes 05/18/2015
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| : 15-00409 Technical Specification for Self-Cleaning Service Water Strainer 02/16/2015
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| : 15-00664 Standing Order:
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| : Restrictions on Use of an EDG to Supply Nonessential 4160 V Busses
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| : 2/27/2015 15-00807 Pipe Stress Analysis for Decay Heat Coolers and Attached DH/LPI and CCW Piping and Pipe Stress Analysis for Decay Heat Flush Piping for 10"
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| : GCB-1
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| : 05/19/2015 15-00915 Emergency Feedwater System 09/16/2016 15-01313 Modify Hanger 5-GBD-2-H16 04/23/2015
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| : 15-01708 Pipe Stress Analysis Sump Pump Piping 09/24/2015
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| : 15-03646 Pipe Stress Analysis 01/06/2016 16-01379 Install Freeze Seal on Demineralized Water line 4"
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| : HCD-4 to Facilitate
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| : WO 200610327
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| : 04/25/2016 16-01483 Serious Station Fire Procedure 05/04/2016 16-02041 Install Temporary Modification to Defeat EDGs Crank Case Pressure Trip
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| : 06/21/2016 16-02042 Compensatory Action - Preclude EDG Crank Case Pressure Trip during Tornado Watch
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| : 06/16/2016 16-00616 Backing Plates for Unused Instrument Locations on Cabinet
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| : C5718 03/07/2016 16-01189 Pipe Stress Analysis Report 04/12/2016 16-02566 Permanently Disable EDGs Crank Case Pressure Trip 08/23/2016 16-02882 Pressurizer Operating Procedure 09/19/2016 16-02967 Spent Fuel Storage System Incorporation 12/28/2016
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| : 10
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| : CFR 50.59 SCREENINGS
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| : Number Description or Title Date 17-01485 Modify Integrated Control System (ICS0 Steam Generator Operate Range High Level Limit from 90% to 96%
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| : 05/11/2017 17-01851 Security Event or Threats 06/12/2017 17-02024 Adjusted Minimum Level for Emergency Diesel Generator Day Tanks 06/22/2017 17-02210 Reactor Vessel Head Drop Analysis 07/19/2017 17-02263 Station Blackout Diesel Generator Operating Procedure 07/24/2017
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| : CALCULATIONS
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| : Number Description or Title Revision 51 Pipe Stress Analysis Report 20 51 Pipe Stress Analysis Report 20, Addendum A01
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| : C-CSS-
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| : 049.02-066 Pipe Stress Analysis for Decay Heat Flush Piping for 10"
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| : GCB-1
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| : 84C Pipe Stress Analysis 11
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| : C-CSS-049.02-064 Pipe Stress Analysis for Decay Heat Pump P42-2 Recirculation Piping 0 C-CSS-049.02-065 Pipe Stress Analysis for Decay Heat Pump P42-1 Recirculation Piping 0 C-NSA-060.05-010 Containment Vessel Analysis 7
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| : C-NSA-060.05-010 Containment Vessel Analysis 8
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| : C-CSS-020.12-004 Pipe Stress Analysis Sump Pump Piping 1
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| : C-CSS-020.12-007 Pipe Stress Analysis Sump Pump Piping 0
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| : C-CSS-062.01-025 Reactor Vessel Head Drop Analysis 2, Addendum A01
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| : C-CSS-
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| : 099.16-064 Backing Plates for Unused Instruments on Cabinets C5718 &
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| : C5720 2, Addendum A02
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| : CORRECTIVE ACTION PROGRAM DOCUMENTS INITIATED DURING INSPECTION
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| : Number Description or Title Date 2017-09668 2017
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| : NRC 10CR50.59: Design Evaluation for Pressurizer Spray Piping to Pressurizer Nozzle and Cold Leg Nozzle Does Not Use Latest Piping Loads"
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| : 09/20/2017
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| : CORRECTIVE ACTION PROGRAM DOCUMENTS REVIEWED
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| : Number Description or Title Date 2013-06458 Low Margin for the Battery Room Minimum Temperature 04/24/2013 2014-00239 NRC Identified Low Temperatures in Battery Room B 01/07/2014 2014-16898 2015 CDBI SA: Service Water Strainer Maximum Flowrate 11/11/2014 2016-03257 AREVA Customer Service Bulletin 16-01 03/09/2016
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| : 2017-02971 OTSG Monitoring - Cycle 20 Level Trending 03/16/2017
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| : DRAWINGS Number Description or Title Revision
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| : OS-045 Operational Schematic Primary and Demineralized Water System 49
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| : OTHER DOCUMENTS
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| : Number Description or Title Date B&W
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| : 58007800 Casualty Analysis for Toledo Edison Control Rod Drive Electrical System
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| : 06/1973 M-237Q Digital Control Rod Drive Control System Performance Test
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| : RAD 14-04107 Spent Fuel Pool Cooling Malfunctions 12/08/2014
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| : RAD 14-04284 Technical Specification for Station Blackout Diesel Generator System
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| : 2/19/2014
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| : RAD 15-00664 Standing Order:
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| : Restrictions on Use of an EDG to Supply Nonessential 4160 V Busses
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| : 2/27/2015
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| : RAD 15-00915 Emergency Feedwater System 09/13/2016
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| : RAD 16-01483 Serious Station Fire Procedure 05/04/2016
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| : RAD 16-02041 Install Temporary Modification to Defeat EDGs Crank Case Pressure Trip
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| : 06/21/2016
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| : RAD 16-02042 Compensatory Action to Remove EDGs Crank Case Pressure Trip during Tornado Watch
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| : 06/16/2016
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| : RAD 16-02566 Permanently Disable EDGs Crank Case Pressure Trip 08/23/2016
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| : RAD 16-02882 Pressurizer Operating Procedure 09/19/2016
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| : RAD 16-02967 Spent Fuel Storage System Incorporation 12/28/2016
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| : RAD 17-01851 Security Events or Threats 06/12/2017
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| : RAD 17-02024 Adjusted Minimum Level for Emergency Diesel Generator Day Tanks
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| : 06/22/2017
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| : RAD 17-02263 Station Blackout Diesel Generator Operating Procedure 07/24/2017
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| : RAD 13-04729 36 Inch Main Steam Line Break Rooms 601/602 01/15/2014
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| : PROCEDURES
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| : Number Description or Title Revision
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| : NNOBP-LP-4003A FENOC 10
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| : CFR 50.59 User Guidelines 8
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| : DB-OP-02012 STM GEN/SFRCS Alarm Panel 12 Annunciator 18
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| }} | | }} |
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Category:Inspection Report
MONTHYEARIR 05000346/20244032024-09-27027 September 2024
Security Baseline Inspection Report 05000346/2024403
IR 05000346/20240052024-08-22022 August 2024
Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2024005)
IR 05000346/20240022024-08-0101 August 2024
Integrated Inspection Report 05000346/2024002
IR 05000346/20244012024-07-30030 July 2024
Security Baseline Inspection Report 05000346/2024401
IR 05000346/20240012024-05-0303 May 2024
Integrated Inspection Report 05000346/2024001
IR 05000346/20230062024-02-28028 February 2024
Re-Issue Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006)
IR 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
IR 05000346/20234022023-12-19019 December 2023
Cyber Security Inspection Report 05000346/2023402
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
IR 05000346/20234012023-09-13013 September 2023
Security Baseline Inspection Report 05000346/2023401 (Public)
IR 05000346/20230112023-08-30030 August 2023
Biennial Problem Identification and Resolution Inspection Report 05000346/2023011
IR 05000346/20230052023-08-24024 August 2023
Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2023005)
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)
IR 05000346/20230022023-07-27027 July 2023
Integrated Inspection Report 05000346/2023002
IR 05000346/20235012023-06-13013 June 2023
Emergency Preparedness Biennial Exercise Inspection Report 05000346/2023501
IR 05000346/20230102023-05-0909 May 2023
Commercial Grade Dedication Inspection Report 05000346/2023010
IR 05000346/20230012023-05-0101 May 2023
Integrated Inspection Report 05000346/2023001 and 07200014/2022001
ML23096A1382023-04-11011 April 2023
Review of the Spring 2022 Steam Generator Tube Inspection Report
IR 05000346/20220062023-03-0101 March 2023
Annual Assessment Letter for Davis-Besse Nuclear Power Station, Unit 1 (Report 05000346/2022006)
IR 05000346/20220912023-02-10010 February 2023
NRC Inspection Report 05000346/2022091 and Apparent Violation
IR 05000346/20220042023-02-0909 February 2023
Integrated Inspection Report 05000346/2022004 and 07200014/2022001
IR 05000346/20224042023-02-0808 February 2023
Material Control and Accounting Program Inspection Report 05000346/2022404
IR 05000346/20224032023-01-23023 January 2023
Security Baseline Inspection Report 05000346/2022403
IR 05000346/20220112023-01-0505 January 2023
Triennial Fire Protection Inspection Report 05000346/2022011
IR 05000346/20220032022-11-10010 November 2022
Integrated Inspection Report 05000346/2022003
IR 05000346/20220402022-11-10010 November 2022
95001 Supplemental Inspection Report 05000346/2022040 and Follow-Up Assessment Letter
IR 05000346/20220102022-11-0202 November 2022
Design Basis Assurance Inspection (Programs) Inspection Report 05000346/2022010
IR 05000346/20224402022-10-0404 October 2022
NRC Supplemental Inspection (95001) Interim Report 05000346/2022440
IR 05000346/20220052022-08-25025 August 2022
Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2022005)
IR 05000346/20220022022-08-11011 August 2022
Integrated Inspection Report 05000346/2022002
ML22208A0652022-07-27027 July 2022
Notification of NRC Fire Protection Team Inspection Request for Information: Inspection Report 05000346/2022011
IR 05000346/20220122022-06-30030 June 2022
Phase III 71003 License Renewal Report 05000346/2022012
IR 05000346/20224012022-05-17017 May 2022
Security Baseline Inspection Report 05000346/2022401
IR 05000346/20220012022-05-12012 May 2022
Integrated Inspection Report 05000346/2022001
IR 05000346/20223012022-04-12012 April 2022
NRC Initial License Examination Report 05000346/2022301
IR 05000346/20210062022-03-0202 March 2022
Annual Assessment Letter for Davis-Besse Nuclear Power Station, Unit 1 (Report 05000346/2021006)
IR 05000346/20210922022-03-0101 March 2022
EA-21-155 Davis Besse - Final Significance Determination of White Finding, Notice of Violation and Assessment Follow Up Letter, NRC Inspection Report 50000346/2021092
IR 05000346/20210042022-02-0909 February 2022
Integrated Inspection Report 05000346/2021004 and Exercise of Enforcement Discretion
ML22032A3142022-02-0101 February 2022
Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information Inspection Report 05000346/2022010
IR 05000346/20210122022-01-31031 January 2022
Temporary Instruction 2515/194 Inspection Report 05000346/2021012
IR 05000346/20210912021-12-17017 December 2021
NRC Inspection Report (05000346/2021091) Preliminary Greater than Green Finding
IR 05000346/20210902021-12-16016 December 2021
Reissue Davis-Besse NRC Inspection Report (05000346/2021090) Preliminary White Finding
ML21340A2212021-12-0909 December 2021
NRC Inspection Report (05000346/2021090) Preliminary White Finding
IR 05000346/20214042021-12-0909 December 2021
Security Baseline Inspection Report 05000346/2021404
IR 05000346/20210502021-11-19019 November 2021
Special Inspection Reactive Report 05000346/2021050 and Apparent Violation
IR 05000346/20210032021-11-10010 November 2021
Integrated Inspection Report 05000346/2021003
IR 05000346/20210112021-11-0101 November 2021
Design Basis Assurance Inspection (Teams) Inspection Report 05000346/2021011
2024-09-27
[Table view]
Category:Letter
MONTHYEARML24303A3282024-10-29029 October 2024
Information Request for the Cyber Security Baseline Inspection Identification to Perform Inspection
ML24281A0662024-10-0404 October 2024
EN 57363 - MPR Associates, Inc. Report in Accordance with 10 CFR Part 21 on Incomplete Dedication of Contactors Supplied as Basic Components
IR 05000346/20244032024-09-27027 September 2024
Security Baseline Inspection Report 05000346/2024403
ML24269A0552024-09-25025 September 2024
Submittal of the Updated Final Safety Analysis Report, Revision 35
05000346/LER-2021-001-01, Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground2024-09-19019 September 2024
Emergency Diesel Generator Speed Switch Failure Due to Direct Current System Ground
ML24134A1522024-09-17017 September 2024
Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter
ML24260A2382024-09-16016 September 2024
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[Table view] |
Text
UNITED STATES ber 11, 2017
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION EVALUATIONS OF CHANGES, TESTS, AND EXPERIMENTS BASELINE INSPECTION REPORT 05000346/2017010
Dear Mr. Bezilla:
On September 22, 2017 the U.S. Nuclear Regulatory Commission (NRC) completed an Evaluations of Changes, Tests, and Experiments inspection at your Davis-Besse Nuclear Power Station. The enclosed inspection report documents the inspection results which were discussed on September 22, 2017, with you and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
The NRC inspectors did not identify any findings or violations of more than minor significance.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-346 License No. NPF-3
Enclosure:
IR 05000346/2017010
REGION III==
Docket No: 50-346 License No: NPF-3 Report No: 05000346/2017010 Licensee: FirstEnergy Nuclear Operating Company Facility: Davis-Besse Nuclear Power Station Location: Oak Harbor, OH Dates: September 18-22, 2017 Inspectors: J. Bozga, Senior Reactor Inspector (Lead)
J. Benjamin, Senior Reactor Inspector J. Gilliam, Reactor Inspector N. Khan, Electrical Engineer (Observer)
Approved by: Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Enclosure
SUMMARY
Inspection Report 05000346/2017010; 09/18/2017-09/22/2017; Davis-Besse Nuclear Power
Station; Evaluations of Changes, Tests, and Experiments.
This report covers a 1-week announced evaluations of changes, tests, and experiments baseline inspection. The inspection was conducted by Region III based engineering inspectors.
The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 6, dated July 201
NRC-Identified
and Self-Revealed Findings No findings were identified.
Licensee-Identified Violations
No violations were identified.
REPORT DETAILS
REACTOR SAFETY
1R17 Evaluations of Changes, Tests, and Experiments
Main article: IP 71111.17T
.1 Evaluation of Changes, Tests, and Experiments
a. Inspection Scope
The inspectors reviewed 4 evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR), Part 50, Section 59, to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The inspectors also reviewed screenings and applicability determinations where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The inspectors reviewed these documents to determine if:
- the changes, tests, and experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required;
- the safety issue requiring the change, tests or experiment was resolved;
- the licensee conclusions for evaluations of changes, tests, and experiments were correct and consistent with 10 CFR 50.59; and
- the design and licensing basis documentation was updated to reflect the change.
The inspectors used, in part, Nuclear Energy Institute 96-07, Guidelines for 10 CFR 50.59 Implementation, Revision 1, to determine acceptability of the completed evaluations, and screenings. The Nuclear Energy Institute document was endorsed by the U.S. Nuclear Regulatory Commission in Regulatory Guide 1.187, Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments, dated November 2000. The inspectors also consulted Part 9900 of the U.S. Nuclear Regulatory Commission Inspection Manual, 10 CFR Guidance for 10 CFR 50.59, Changes, Tests, and Experiments.
This inspection constituted 30 samples of evaluations, screenings, and/or applicability determinations as defined in Inspection Procedure 71111.17-05.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES (OA)
4OA2 Problem Identification and Resolution
.1 Routine Review of Condition Reports
a. Inspection Scope
The inspectors reviewed several corrective action process documents that identified or were related to 10 CFR 50.59 evaluations. The inspectors reviewed these documents to evaluate the effectiveness of corrective actions related to evaluations of changes, tests, and experiments. In addition, corrective action documents written on issues identified during the inspection were reviewed to verify adequate problem identification and incorporation of the problems into the corrective action system. The specific corrective action documents that were sampled and reviewed by the inspectors are listed in the attachment to this report.
b. Findings
No findings of significance were identified.
4OA6 Management Meetings
.1 Exit Meeting Summary
On September 22, 2017, the inspectors presented the inspection results to Mr. M. Bezilla, Site Vice President, and other members of the licensee staff. The licensee personnel acknowledged the inspection results presented and did not identify any proprietary content. The inspectors confirmed that all proprietary material reviewed during the inspection was returned to the licensee staff.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
- M. Bezilla, Site Vice President
- G. Wolf, Regulatory Compliance Supervisor
- D. Blakely, Engineering Analysis Supervisor
- J. Sturdavant, Regulatory Compliance Specialist
LIST OF ITEMS
OPENED, CLOSED AND DISCUSSED
Opened, Closed and
Discussed
None LIST OF ACRONYMS USED CFR Code of Federal Regulations
LIST OF DOCUMENTS REVIEWED
