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Category:Letter type:L
MONTHYEARL-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024
Submittal of Quality Assurance Program Manual, Revision 30
L-24-032, Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report2024-07-15015 July 2024
Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report
L-24-063, License Amendment Request to Remove the Table of Contents from the Technical Specifications2024-07-0808 July 2024
License Amendment Request to Remove the Table of Contents from the Technical Specifications
L-24-024, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-19019 June 2024
Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-23-214, Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2024-06-0505 June 2024
Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements
L-24-019, Unit No.1 - Report of Facility Changes, Tests, and Experiments2024-05-22022 May 2024
Unit No.1 - Report of Facility Changes, Tests, and Experiments
L-24-072, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 20232024-05-15015 May 2024
Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 2023
L-24-111, Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-05-15015 May 2024
Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
L-24-031, Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage2024-05-14014 May 2024
Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage
L-24-069, Occupational Radiation Exposure Report for Year 20232024-04-30030 April 2024
Occupational Radiation Exposure Report for Year 2023
L-24-018, Submittal of Core Operating Limits Report, Cycle 24, Revision 02024-04-16016 April 2024
Submittal of Core Operating Limits Report, Cycle 24, Revision 0
L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024
Annual Notification of Property Insurance Coverage
L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024
Retrospective Premium Guarantee
L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023
Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station
L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023
Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
L-23-215, Changes to Emergency Plan2023-10-19019 October 2023
Changes to Emergency Plan
L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023
Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023
Quality Assurance Program Manual
L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023
Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023
Submittal of Fifth Ten Year Inservice Testing Program
L-23-034, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-13013 June 2023
2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-23-135, Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-31031 May 2023
Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
L-23-065, Annual Financial Report2023-05-22022 May 2023
Annual Financial Report
L-23-101, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 20222023-05-12012 May 2023
Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 2022
L-23-131, Readiness for Resumption of NRC Supplemental Inspection2023-05-12012 May 2023
Readiness for Resumption of NRC Supplemental Inspection
L-23-092, Occupational Radiation Exposure Report for Year 20222023-04-27027 April 2023
Occupational Radiation Exposure Report for Year 2022
L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023
Submittal of the Decommissioning Funding Status Reports
L-23-037, and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2023-03-29029 March 2023
and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments
L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023
Annual Notification of Property Insurance Coverage
L-23-059, Response to Apparent Violation in NRC Inspection Report 05000346/2022091; EA 23-0022023-03-0909 March 2023
Response to Apparent Violation in NRC Inspection Report 05000346/2022091; EA 23-002
L-22-212, CFR 50.55a Request RP-5 Regarding Inservice Pump Testing2023-03-0606 March 2023
CFR 50.55a Request RP-5 Regarding Inservice Pump Testing
L-23-048, Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2023-03-0101 March 2023
Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report
L-23-057, Energy Harbor Nuclear Corp Retrospective Premium Guarantee2023-02-20020 February 2023
Energy Harbor Nuclear Corp Retrospective Premium Guarantee
L-22-253, Submittal of Pressure and Temperature Limits Report, Revision 52023-01-10010 January 2023
Submittal of Pressure and Temperature Limits Report, Revision 5
L-22-284, Request for Notice of Enforcement Discretion for Technical Specification 3.7.9, Ultimate Heat Sink (UHS)2022-12-28028 December 2022
Request for Notice of Enforcement Discretion for Technical Specification 3.7.9, Ultimate Heat Sink (UHS)
L-22-211, Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2022-09-29029 September 2022
Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report
L-22-216, Submittal of Pressure and Temperature Limits Report. Revision 42022-09-27027 September 2022
Submittal of Pressure and Temperature Limits Report. Revision 4
L-22-213, Occupational Radiation Exposure Report for Year 2021 - Correction2022-09-23023 September 2022
Occupational Radiation Exposure Report for Year 2021 - Correction
L-22-129, Submittal of the Updated Final Safety Analysis Report, Revision 342022-09-20020 September 2022
Submittal of the Updated Final Safety Analysis Report, Revision 34
L-22-194, Submittal of Supplemental Information for the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events2022-09-19019 September 2022
Submittal of Supplemental Information for the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events
L-22-203, Submittal of Evacuation Time Estimates2022-09-12012 September 2022
Submittal of Evacuation Time Estimates
L-22-050, Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual2022-08-0909 August 2022
Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual
L-22-152, Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan2022-07-0505 July 2022
Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan
L-22-068, Cycle 22 and Refueling Outage 22 Inservice Inspection Summary Report2022-06-30030 June 2022
Cycle 22 and Refueling Outage 22 Inservice Inspection Summary Report
L-22-037, 2021 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2022-06-30030 June 2022
2021 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-22-149, Post Accident Monitoring Report2022-06-23023 June 2022
Post Accident Monitoring Report
L-22-153, Readiness for NRC Supplemental Inspection Required for a White Finding2022-06-22022 June 2022
Readiness for NRC Supplemental Inspection Required for a White Finding
L-22-098, Withdrawal of Proposed Inservice Inspection Alternative RR-A22022-06-22022 June 2022
Withdrawal of Proposed Inservice Inspection Alternative RR-A2
L-22-136, Steam Generator Tube Circumferential Crack Report - Spring 2022 Refueling Outage2022-06-0707 June 2022
Steam Generator Tube Circumferential Crack Report - Spring 2022 Refueling Outage
L-22-092, Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 20212022-05-16016 May 2022
Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 2021
2024-08-27
[Table view]
Category:Plant Status Report
MONTHYEARL-16-094, Docket No. 50-346, License No. NPF-3 - Report of Facility Changes. Tests. and Experiments2016-06-0707 June 2016
Docket No. 50-346, License No. NPF-3 - Report of Facility Changes. Tests. and Experiments
L-15-101, Submittal of the Decommissioning Funding Status Reports for Beaver Valley, Units 1 and 2, Davis-Besse and Perry, Unit 12015-03-31031 March 2015
Submittal of the Decommissioning Funding Status Reports for Beaver Valley, Units 1 and 2, Davis-Besse and Perry, Unit 1
2016-06-07
[Table view] |
Text
FENOC' 5501 North State Route 2 RrstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449 Brian D. Boles 419-321-7676 Vice President, Fax: 419-321-7582 Nuclear June 7, 2016 L-16-094 10 CFR 50.59(d)(2)
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station, Unit No. 1 Docket No. 50-346, License No. NPF-3 Report of Facility Changes. Tests. and Experiments In accordance with 10 CFR 50.59(d)(2), FirstEnergy Nuclear Operating Company (FENOC) hereby submits the Report of Facility Changes, Tests, and Experiments for the Davis-Besse Nuclear Power Station, Unit No. 1. The attached report covers the period of May 27, 2014 through May 23, 2016.
There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Thomas A.
Lentz, Manager - Fleet Licensing at (330) 315-6810.
Sincerely,
~~~-4Z.-
Brian D. Boles
Attachment:
Davis-Besse Nuclear Power Station, Unit No. 1 Report of Facility Changes, Tests, and Experiments cc: Nuclear Regulatory Commission (NRC) Region Ill Administrator NRC Resident Inspector NRC Project Manager Utility Radiological Safety Board
Attachment L-16-094 Davis-Besse NuClear Power Station, Unit No. 1 Report of Facility Changes, Tests, and Experiments
(
Page 1 of 2
Title:
Installation of Digital Control Rod Drive Control System Activity
Description:
The control rod drive (CRD) system was replaced with a digital control rod drive control system (DCRDCS). The new DCRDCS is functionally similar to the original system with the exception that the new system has an improved design with two single rod power supply (SRPS) modules for each CRD motor. This eliminates the need for the auxiliary power supply and the rod transfer function, simplifying rod control operations. Each SRPS has independent fusing and breakers for each phase and is modular for easy on-line maintenance. Each half of the power supply pair is powered frnm one of two different AC power inputs, thus providing reliable redundant power.
The replacement DCRDCS changes the analog controls that were utilized in the original system to the digital controls of the replacement system. Digital controls are accomplished through the use of triple modular redundant (TMR) digital controllers and software. The new system has a more reliable design in that there are two SRPS modules for each control rod drive mechanism (CROM) motor, which eliminates the need for the auxiliary power supply and rod transfer functions, simplifying rod control operations.
Summary of Evaluation:
The use of redundant TMR controllers and reliable SRPSs was reviewed under a reliability study as well as being assessed through the completion of extensive system testing, which showed that this change does not result in an adverse effect on the frequency of occurrence of misaligned CRDMs or the frequency of occurrence of uncontrolled control rod assembly withdrawal.
No increase in any accident frequency or malfunction likelihood of a system, structure, or component (SSC) important to safety was found based on DCRDCS reliability studies and failure modes and effects analyses (FMEA) associated with the TMR design, single rod power supply design, and position indication panel design.
No increase in the radiological consequences of an accident or malfunction was found.
The CRD system trip response, which is relied on in the accident analysis, is not altered.
Additionally, the worst-case accident of all control rod assemblies being withdrawn at once is evaluated and thus bounds the change since the number of control rods and their travel rates are not being altered.
Attachment L-16-094 Page 2of2 The possibility for an accident of a different type is not created by this change. The worst-case rod withdrawal accidents are bounded by any rod withdrawal accidents that could result from the change, since uncontrolled withdrawal of all control rods is already analyzed. Additionally, the reactor trip breaker functions are not altered by this change, and therefore the control rod trip function is unaffected.
Based on results of the DCRDCS FMEA and the system acceptance testing where the system was placed in unusual configurations, the change results in failure modes and malfunctions that are equivalent to those of the original system, and the credible malfunction results are bounded by those of the existing system. Therefore, the DCRDCS does not create a possibility for a malfunction of an SSC important to' safety with a different result.
The change does not result in a design basis limit for a fission product barrier being exceeded or altered. The change replaces the existing CRD system hardware and does not alter any fission product barrier, barrier analysis result, or revise any design basis limits. The CRDMs and related pressure boundary were not altered by this change.
It was determined that this change does not involve revising or replacing a UFSAR-described evaluation methodology used in establishing the design basis or in the safety analysis. The proposed activity does not involve altering any plant parameters or environmental conditions such that ~ny SSC is operated in other than its normal analyzed mode nor are any reference bounds, analyses, or descriptions adversely affected by this change.
The installation and use of the DCRDCS does not adversely affect any UFSAR-de~cribed design functions. The ability of the DCRDCS to provide for the controlled withdrawal, controlled insertion, and holding of the control rod assemblies as stated in UFSAR Sections 1.2.4.2.4, 4.2.3.2 and 4.2.3.5.1 is not adversely affected by the change. The control rod trip function is not adversely altered by this change. The modification does not adversely affect the ability of the DCRDCS to provide continuous rod position indication, as well as indicate when each rod is fully withdrawn, fully inserted, enabled and whether a rod position asymmetry alarm condition is present for each CRD as required in UFSAR Sections 4.2.3.2, 4.3.5.3, and 7.7.1.3.2. The replacement DCRDCS is a functional equivalent to the existing system providing all required information and controls to the operator using the same functional priorities as the original system to manage core reactivity as stated in the UFSAR.
