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| {{Adams | | {{Adams |
| | number = ML21207A006 | | | number = ML21047A473 |
| | issue date = 07/26/2021 | | | issue date = 02/16/2021 |
| | title = Design Basis Assurance Inspection (Teams) Inspection Report 05000259/2021010 and 05000260/2021010 and 05000296/2021010 | | | title = Notification of Browns Ferry Nuclear Power Plant Design Bases Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000259/2021010, 05000260/2021010, and 05000296/2021010 |
| | author name = Baptist J | | | author name = Baptist J |
| | author affiliation = NRC/RGN-II/DRS | | | author affiliation = NRC/RGN-II/DRS/EB1 |
| | addressee name = Barstow J | | | addressee name = Barstow J |
| | addressee affiliation = Tennessee Valley Authority | | | addressee affiliation = Tennessee Valley Authority |
| Line 10: |
Line 10: |
| | license number = DPR-033, DPR-052, DPR-068 | | | license number = DPR-033, DPR-052, DPR-068 |
| | contact person = | | | contact person = |
| | case reference number = EPID I-2021-010-0038
| |
| | document report number = IR 2021010 | | | document report number = IR 2021010 |
| | document type = Inspection Report | | | document type = Inspection Plan, Letter |
| | page count = 17 | | | page count = 5 |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:July 26, 2021 | | {{#Wiki_filter:February 16, 2021 |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| BROWNS FERRY NUCLEAR PLANT - DESIGN BASIS ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000259/2021010 AND 05000260/2021010 AND 05000296/2021010 | | NOTIFICATION OF BROWNS FERRY NUCLEAR POWER PLANT DESIGN BASES ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION INSPECTION REPORT 05000259/2021010, 05000260/2021010, AND 05000296/2021010 |
|
| |
|
| ==Dear Mr. Barstow:== | | ==Dear Mr. Barstow:== |
| On June 29, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Browns Ferry Nuclear Plant and discussed the results of this inspection with Mr. Chris Dunn and other members of your staff. The results of this inspection are documented in the enclosed report.
| | The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC) |
| | Region II staff will conduct a Design Bases Assurance Inspection (DBAI) at your Browns Ferry Nuclear Power Plant during the weeks of May 17 - 21, and June 7 - 11, 2021. |
|
| |
|
| No findings or violations of more than minor significance were identified during this inspection.
| | Mr. Marcus Riley, a reactor inspector from the NRCs Region II office, will lead the inspection team. The inspection will be conducted in accordance with Inspection Procedure 71111.21M, Design Bases Assurance Inspection (Teams), dated December 8, 2016 (ADAMS ML16238A320). |
|
| |
|
| 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 Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
| | The inspection will evaluate the capability of components that have been modified and risk-significant/low-margin components to function as designed and to support proper system operation. The inspection will also include a review of selected operator actions, operating experience, and modifications. |
|
| |
|
| Sincerely,
| | During a telephone conversation on February 11, 2021, with Mr. Denzel Housley, we confirmed arrangements for an information-gathering site visit and the two-week onsite inspection. The schedule is as follows: |
| /RA/
| | * Information-gathering visit: Week of April 26 - 30, 2021 |
| | * |
| | Onsite weeks: Weeks of May 17 - 21, and June 7 - 11, 2021 |
|
| |
|
| James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety
| | The purpose of the information-gathering visit is to meet with members of your staff to identify components that have been modified, risk-significant components, and operator actions. |
|
| |
|
| Docket Nos. 05000259 and 05000260 and 05000296 License Nos. DPR-33 and DPR-52 and DPR-68
| | Information and documentation needed to support the inspection will also be identified. |
|
| |
|
| ===Enclosure:===
| | Mr. Andy Rosebrook, a Region II Senior Risk Analyst, will support Mr. Riley during the information-gathering visit to review probabilistic risk assessment data and identify components to be examined during the inspection. Additionally, during the onsite weeks, time will be needed on the plant-referenced simulator in order to facilitate the development of operator action-based scenarios. The enclosure lists documents that will be needed prior to the information-gathering visit. |
| As stated
| |
|
| |
|
| ==Inspection Report==
| | Please provide the referenced information to the Region II Office by Friday, April 16, 2021. |
| Docket Numbers:
| |
| 05000259, 05000260 and 05000296
| |
|
| |
|
| License Numbers:
| | Additional documents will be requested following the information-gathering visit. The inspectors will try to minimize your administrative burden by specifically identifying only those documents required for inspection preparation. The additional information will be needed in the Region II office by Friday, May 7, 2021, to support the inspection teams preparation week. During the information-gathering trip, Mr. Riley will also discuss the following inspection support administrative details, as applicable: (1) availability of knowledgeable plant engineering and licensing personnel to serve as points of contact during the inspection; (2) method of tracking inspector requests during the inspection; (3) licensee computer access; (4) working space; (5) |
| DPR-33, DPR-52 and DPR-68
| | arrangements for site access; and (6) other applicable information. |
|
| |
|
| Report Numbers:
| | 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. |
| 05000259/2021010, 05000260/2021010 and 05000296/2021010
| |
|
| |
|
| Enterprise Identifier: I-2021-010-0038
| | Thank you for your cooperation in this matter. If you have any questions, regarding the information requested or the inspection, please contact Mr. Riley at 404-997-4888 or contact me at 404-997-4506. |
|
| |
|
| Licensee:
| | Sincerely, |
| Tennessee Valley Authority
| | /RA/ |
|
| |
|
| Facility:
| | James Baptist, Chief |
| Browns Ferry Nuclear Plant
| |
|
| |
|
| Location:
| | Engineering Branch 1 |
| Athens, AL
| |
|
| |
|
| Inspection Dates:
| | Division of Reactor Safety |
| May 17, 2021 to June 11, 2021
| |
|
| |
|
| Inspectors:
| | Docket Nos.: 50-259, 50-260, 50-296 License Nos.: DPR-33, DPR-52, DPR-68 |
| C. Baron, Contractor
| |
|
| |
|
| D. Bollock, Senior Reactor Operations Engineer
| | Enclosure: |
| | Notification of Browns Ferry Nuclear Power Plant, Design Bases Assurance Inspection (Teams) |
|
| |
|
| W. Deschaine, Senior Resident Inspector
| | cc: Distribution via Listserv |
|
| |
|
| S. Kobylarz, Contractor
| | ML21047A473 X |
| | SUNSI Review |
|
| |
|
| R. Patterson, Senior Reactor Inspector
| | X Non-Sensitive |
|
| |
|
| J. Winslow, Reactor Systems Engineer
| | Sensitive |
|
| |
|
| Approved By:
| | X Publicly Available |
| James B. Baptist, Chief
| |
| Engineering Branch 1
| |
| Division of Reactor Safety
| |
|
| |
|
| =SUMMARY=
| | Non-Publicly Available |
| The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design basis assurance inspection (teams) inspection at Browns Ferry Nuclear Plant, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
| |
|
| |
|
| ===List of Findings and Violations===
| | OFFICE RII/DRS RII/DRS |
| No findings or violations of more than minor significance were identified.
| |
|
| |
|
| ===Additional Tracking Items===
| | NAME M. Riley J. Baptist |
| None.
| |
|
| |
|
| =INSPECTION SCOPES=
| | DATE 02/12/2021 02/12/2021 |
|
| |
|
| Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
| | Enclosure INFORMATION REQUEST FOR BROWNS FERRY NUCLEAR POWER PLANT DESIGN BASES ASSURANCE INSPECTION (TEAMS) |
|
| |
|
| Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
| | Please provide the information electronically in.pdf files, Excel, or other searchable format on CDROM (or FTP site, SharePoint, etc.). The CDROM (or website) should be indexed and hyperlinked to facilitate ease of use. The requested items below, identified with an asterisk (*), |
| | should have a date range from January 1, 2018, until present. |
|
| |
|
| ==REACTOR SAFETY==
| | 1. |
| ===71111.21M - Design Bases Assurance Inspection (Teams)
| | * List and brief description of permanent and field work completed plant modifications including permanent plant changes, design changes, set point changes, procedure changes, equivalency evaluations, suitability analyses, calculations, and commercial grade dedications. Include an index of systems (system numbers/designators and corresponding names), the safety classification for each modification, and type of modification. |
|
| |
|
| The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:
| | 2. |
|
| |
|
| Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (4 Samples)
| | From your most recent probabilistic safety analysis (PSA) excluding external events and fires: |
|
| |
|
| (1)250V DC Reactor Motor Operated Valve (RMOV) Board 2B
| | a. Two risk rankings of components from your site-specific PSA: one sorted by Risk Achievement Worth (RAW), and the other sorted by Birnbaum Importance |
| * Material condition and configuration (e.g., visual inspection during a walkdown)
| |
| * Operating environment
| |
| * Consistency between station documentation (e.g. procedures) and vendor specifications
| |
| * Maintenance effectiveness
| |
| * Corrective maintenance records, and corrective action history
| |
| * Panel loading
| |
| * Load voltage adequacy
| |
| * Overcurrent protection and coordination
| |
| : (2) Emergency Essential Cooling Water (EECW) Strainers | |
| * Material condition and configuration (e.g., visual inspection during a walkdown by onsite inspector)
| |
| * Consistency between station documentation (e.g. procedures and drawings)and vendor specifications
| |
| * Corrective maintenance records, and corrective action history
| |
| * System Health Reports
| |
| * Compliance with UFSAR, TS, and TS Bases
| |
| * Normal and emergency operating procedures
| |
| * Modifications
| |
| * Completed surveillance tests to ensure acceptance criteria have been met
| |
|
| |
|
| (3)480V RMOV BD 2D
| | b. A list of the top 500 cut-sets |
| * Material condition and configuration (e.g., visual inspection during a walkdown)
| |
| * Operating environment
| |
| * Consistency between station documentation (e.g. procedures) and vendor specifications
| |
| * Maintenance and Preventive Maintenance effectiveness
| |
| * Corrective maintenance records, and corrective action history
| |
| * Breaker short circuit capacity
| |
| * BD (MCC) loading
| |
| * BD (MCC) voltage adequacy
| |
| * Overcurrent protection and coordination
| |
| : (4) Unit 2 Reactor Core Isolation Cooling (RCIC) System Pump 2B
| |
| * Normal and Emergency Operating Procedures
| |
| * Surveillance Test Procedures and Recent Results
| |
| * Inservice Test Procedures and Recent Results
| |
| * Bases for Pump Test Acceptance Criteria
| |
| * Calculation of Pump Capacity
| |
| * Calculation of Pump NPSH
| |
| * Calculation of System Pressure due to Pump Overspeed Condition
| |
| * Operation of RCIC under Station Blackout Conditions
| |
| * Evaluation of RCIC Pump Suction Transfer
| |
| * Material Condition of Pump and Associated Equipment
| |
| * Corrective Action History
| |
|
| |
|
| Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02)===
| | c. A list of the top 500 LERF contributors |
| {{IP sample|IP=IP 71111.21|count=1}}
| |
| : (1) Unit 2 Automatic Depressurization System (ADS) Valves
| |
| * Normal and Emergency Operating Procedures
| |
| * Calculation of Instrument Air Supply and Air Accumulator Capacity
| |
| * Instrument Air Leakage Test Procedures and Recent Results
| |
| * Recent Valve Test Results
| |
| * Evaluation of Electrical Control and Power Supplies
| |
| * Evaluation of Testing of Backup Electrical Control and Power Supplies
| |
| * Corrective Action History
| |
|
| |
|
| ===Modification Review - Permanent Mods (IP Section 02.03) (6 Samples)===
| | 3. |
| : (1) DCN 71425, Upgrade Unit 1/2 Emergency Diesel Generator Fuel Oil Piping Configuration
| |
| : (2) DCN 72338-03, Replacement of 4160V/480V Emergency Shutdown Board 2A & 2B Transformer
| |
| : (3) BFN-19-918-01-U1, High Pressure Coolant Injection Gland Seal Check Valve Addition
| |
| : (4) DCN 69466A, Replace Core Spray and Residual Heat Removal Room Cooler Fan Motors, Fans, and Shafts
| |
| : (5) BFN-1-2020-068-003, Temporary Replacement of Recirculation Loop 1B Flow Measurement (T-Mod)
| |
| : (6) DCN 70747-71, 480V RMOV BD 2A/15D ALT FDR from SD BD
| |
|
| |
|
| ===Review of Operating Experience Issues (IP Section 02.06) (2 Samples)===
| | From your most recent PSA including external events and fires: |
| : (1) NRC IN 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify
| |
| : (2) NRC IN 91-50: A Review of Water Hammer Events After
| |
|
| |
|
| ==INSPECTION RESULTS==
| | a. Two risk rankings of components from your site-specific PSA: one sorted by RAW, and the other sorted by Birnbaum Importance |
| No findings were identified.
| |
|
| |
|
| ==EXIT MEETINGS AND DEBRIEFS==
| | b. A list of the top 500 cut-sets |
| The inspectors verified no proprietary information was retained or documented in this report.
| |
| * On June 29, 2021, the inspectors presented the design basis assurance inspection (teams) inspection results to Mr. Chris Dunn and other members of the licensee staff.
| |
|
| |
|
| =DOCUMENTS REVIEWED=
| | 4. |
|
| |
|
| Inspection
| | Risk ranking of operator actions from your site-specific PSA sorted by RAW and human reliability worksheets for these items |
| Procedure
| |
| Type
| |
| Designation
| |
| Description or Title
| |
| Revision or
| |
| Date
| |
| 71111.21M Calculations
| |
| BFN-1-47E859-1
| |
| Flow Diagram, Emergency Equipment Cooling Water
| |
| Rev. 99
| |
| CDQ-0067-881511
| |
| Seismic Qualification for the Automatic Self-Cleaning
| |
| Strainer
| |
| Rev. 1
| |
| CDQ-0067894672
| |
| Evaluation and Review of Small Bore Unit 0 Piping and
| |
| Supports within the Scope of the System 067 Safe
| |
| Shutdown Boundary
| |
| Rev. 12
| |
| CDQ-1067895300
| |
| Pipe Stress Analysis of Stress Problem No. 1-67-859-1-
| |
| Rev. 3
| |
| CDQ-2067890748
| |
| Strainer Backwash Blowdown Piping at Pumping Station
| |
| Rev. 2
| |
| CDQ0303880436
| |
| Assess the RHRSW and the EECW Piping and
| |
| Components for the Affects of Tornadic Wind-RHRSW
| |
| Pump
| |
| Rev. 2
| |
| CDQ0999910005
| |
| Evaluation of Seismic-Induced Spray Hazards at BFN,
| |
| Unit 2 and Common
| |
| Rev. 3
| |
| CDQ107320021062
| |
| Small Bore Piping and Supports Program System
| |
| Calculation for Seismic Class 1 HPCI System (73) Piping
| |
| Rev. 6
| |
| CDQ107320031063
| |
| Pipe Stress Analysis of Stress Problem N1-173-67R
| |
| Rev. 1
| |
| EDQ0057920034
| |
| 4.16KV and 480V Busload, Voltage Drop and Short
| |
| Circuit Calculation
| |
| Rev. 92
| |
| EDQ024820020042
| |
| 250V DC Unit Battery Load Study
| |
| Rev. 91
| |
| EDQ2000870054
| |
| Control Circuit Voltage Drop Calculations - 250V DC
| |
| circuits
| |
| Rev. 43
| |
| EDQ2000870550
| |
| Cable and Bus Protection/Breaker/Fuse Coordination for
| |
| 250V DC System
| |
| Rev. 54
| |
| EDQ2092900118
| |
| Setpoint and Scaling Calculation for Neutron Monitoring
| |
| System & Recirculation Flaw Loops
| |
| Rev. 37
| |
| EDQ2999870549
| |
| Power Cable Protection Analysis for 480V MCCs
| |
| Rev. 54
| |
| EQD29998801715
| |
| Thermal Overload Heater Calculation
| |
| Rev. 50
| |
| MD-N0026-910163
| |
| Combustible Load Table
| |
| Rev. 71
| |
| MDQ-
| |
| 0000672019000460
| |
| MOV 0-FCV-067-0001/0005/0008/0011, Operator
| |
| Requirements and Capabilities
| |
| Rev. 1
| |
| MDQ-0067890059
| |
| Analytical Limits for the EECW Strainers and Strainer
| |
| Rev. 2
| |
|
| |
|
| Inspection
| | 5. |
| Procedure
| |
| Type
| |
| Designation
| |
| Description or Title
| |
| Revision or
| |
| Date
| |
| Drain Valves Start/Stop Controls
| |
| MDQ0000712012000031 RCIC Pump NPSHa and System Hydraulic Analysis
| |
| (Pump Water Suction and Discharge)
| |
| Rev. 3
| |
| MDQ0000732012000062 Calculation of Effects of Gas Accumulation in ECCS
| |
| Piping
| |
| Rev. 0
| |
| MDQ0032870288
| |
| Control Air Volume and Wall Thickness of Accumulators
| |
| Rev. 14
| |
| MDQ0071910235
| |
| Reactor Core Isolation Cooling System Design
| |
| Pressure/Temperature
| |
| Rev. 12
| |
| MDQ099920040034
| |
| Setpoint Controls Parameters Review Calculation for
| |
| BFN Category 2 Air Operated Valves (AOVs)
| |
| Rev. 17
| |
| MDQ099920040040
| |
| HPCI and RCIC Test Requirements
| |
| Rev. 11
| |
| NDN00099920070032
| |
| BFN Probablistic Risk Assessment - Human Reliability
| |
| Analysis
| |
| Rev. 8
| |
| Corrective Action
| |
| Documents
| |
| 0044691
| |
| 28951
| |
| 0175232
| |
| 200183
| |
| 1648705
| |
| 1649288
| |
| 1649610
| |
| 1652318
| |
| 1369055
| |
| 1406271
| |
| 1499731
| |
| 1500527
| |
| 1557241
| |
| 1606454
| |
| 1607278
| |
| 1613986
| |
| 1614688
| |
| 1617438
| |
| 27370
| |
| 1638651
| |
| 1655591
| |
|
| |
|
| Inspection
| | List of time-critical operator actions with a brief description of each action |
| Procedure
| |
| Type
| |
| Designation
| |
| Description or Title
| |
| Revision or
| |
| Date
| |
| 1656541
| |
| 1656544
| |
| 1658162
| |
| 1658186
| |
| 1658998
| |
| 1664478
| |
| 1665909
| |
| 1676979
| |
| 1687954
| |
| 1688353
| |
| 1695185
| |
| 201387
| |
|
| |
|
| 21012
| | 6. |
| | * List of components with low-design margins (i.e., pumps closest to the design limit for flow or pressure, diesel generator close to design-required output, heat exchangers close to rated design heat removal, and motor-operated valve risk-margin rankings, etc.) and associated evaluations or calculations |
|
| |
|
| 1434874
| | 7. |
| | * List and brief description of Root Cause Evaluations performed 8. |
| | * List and brief description of common-cause component failures that have occurred |
|
| |
|
| 1435350
| | 9. |
| | * List and brief description of Operability Determinations and Functionality Assessments |
|
| |
|
| 1613271
| | 10. *List and reason for equipment that has been classified in maintenance rule (a)(1) status |
|
| |
|
| Corrective Action
| | 11. *List of equipment on the sites Station Equipment Reliability Issues List, including a description of the reason(s) why each component is on that list, and summaries (if available) of your plans to address the issue(s) along with dates added or removed from the issues list |
| Documents
| |
| Resulting from
| |
| Inspection
| |
| 1695185
| |
| A3 RHRSW Lube Oil Strainer Sight Glass
| |
| 1695266
| |
| Control of HPCI and RCIC System Flow Controller
| |
| Settings
| |
| 1695742
| |
| Danger sign was identified on the top of 480V RMOV
| |
| Board 2D
| |
| 1695748
| |
| Review and Evaluate Unit 2 RCIC System CQS Test
| |
| Results
| |
| 1695790
| |
| NRC DBAI Inspection - Minor Correction Needed on
| |
| FPPCIS for ECP 71425
| |
| 1695802
| |
| NRC DBAI 2021 Inspection - Correction Needed to 1/2-
| |
| ARP-9-23A/B/C/D and 0-ARP-25-41A/B/C/D
| |
| 1696259
| |
| Pipe Wrench Laying on Top of the C# EECW Strainers
| |
| Gearbox01
| |
| 1696423
| |
| NRC DBAI Inspection - Incorrect M&TE Number
| |
| Documented in WO 116092256
| |
| 1696542
| |
| 250V Reactor MOV Board 2B board is missing 3
| |
| finishing plugs
| |
| 1696552
| |
| 480V Reactor MOV board 2A missing 1 finishing plug
| |
|
| |
|
| Inspection
| | 12. List of current operator work arounds/burdens |
| Procedure
| |
| Type
| |
| Designation
| |
| Description or Title
| |
| Revision or
| |
| Date
| |
| 1696556
| |
| 480V Reactor MOV board 2D remove RTV from
| |
| Finishing Plug hole and install Finishing Plug
| |
| 1696713
| |
| Request PCRs for RCIC Flowrate Procedures
| |
| 1698638
| |
| MDQ0071910235 Evaluation Didnt Account for
| |
| Tolerance
| |
| 1699579
| |
| Fire seal label is required at the S25932501 penetration
| |
| per MAI-3.4A and is missing
| |
| 1699961
| |
| Fire Seal Penetration R26395139 not conforming to
| |
| design output drawing 0-45E830-27
| |
| 1699971
| |
| Fire Seal Penetration R36395359 not conforming to
| |
| design output drawing 0-45E830-27
| |
| 1700011
| |
| DP Between RCIC Pump Discharge and RPV
| |
| 1700151
| |
| Response to RCIC Overspeed
| |
| 1700334
| |
| RCIC Surveillance Procedure Non-Conservative with
| |
| Respect to TS
| |
| 1700335
| |
| NRC Observation Recirc Temp Mod
| |
| Drawings
| |
| 0-45E830-27
| |
| Conduit & Grounding Cable Trays Fire Stop Dets-SH 14
| |
| Rev. 7
| |
| 0-47E392-1
| |
| Fire Protection - 10 CFR 50 - NFPA 805 Penetration
| |
| Seal Tabular Drawings General Notes and Legend
| |
| Rev. 5
| |
| 0-47E840-3
| |
| Flow Diagram, Fuel Oil System
| |
| Rev. 27
| |
| 0-731E700
| |
| One Line Diagram of DC & Instrument Control AC
| |
| Systems
| |
| Rev. 8
| |
| 1-45E751-3
| |
| Wiring Diagram, 480V Reactor MOV Board 1B
| |
| Rev. 43
| |
| 2-45E712-2
| |
| Wiring Diagram 250V Reactor MOV BD 2B Single Line
| |
| Rev. 35
| |
| 2-47E610-1-1
| |
| Mechanical Control Diagram - Main Steam System
| |
| Rev. 43
| |
| 2-47E610-71-1
| |
| Mechanical Control Diagram - RCIC System
| |
| Rev. 45
| |
| 2-47E610-71-2
| |
| Mechanical Control Diagram - RCIC System
| |
| Rev. 7
| |
| 2-47E801-1
| |
| Flow Diagram - Main Steam
| |
| Rev. 34
| |
| 2-47E813-1
| |
| Flow Diagram - Reactor Core Isolation Cooling System
| |
| Rev. 60
| |
| 2-47W2392-702
| |
| Fire Protection - 10 CFR 50 Appendix R Penetration
| |
| Seal Location Drawings Plan View Area I
| |
| Rev. 1
| |
| 2-47W2392-708
| |
| Fire Protection - 10 CFR 50 Appendix R Penetration
| |
| Seal Location Drawings EL 639
| |
| Rev. 1
| |
|
| |
|
| Inspection
| | 13. Copy of Updated Final Safety Analysis Report |
| Procedure
| |
| Type
| |
| Designation
| |
| Description or Title
| |
| Revision or
| |
| Date
| |
| 2-47W2392-716
| |
| Fire Protection - 10 CFR 50 Appendix R Penetration
| |
| Seal Tabular Drawings EL 639
| |
| Rev. 3
| |
| 2-730E929-2
| |
| Automatic Blowdown System
| |
| Rev. 24
| |
| 2-730E929-3
| |
| Elementary Diagram - Automatic Blowdown System
| |
| Rev. 16
| |
| 2-730E929-4
| |
| Automatic Blowdown System
| |
| Rev. 18
| |
| BFN-0-47E610-67-2
| |
| Mechanical Control Diagram, Emergency Equipment
| |
| Cooling Water
| |
| Rev. 38
| |
| BFN-1-47E610-67-1
| |
| Mechanical Control Diagram, Emergency Equipment
| |
| Cooling Water
| |
| Rev. 50
| |
| BFN-1-47E812-1-CC
| |
| Flow Diagram, High Pressure Coolant Injection System
| |
| Rev. 48
| |
| BFN-2-45E751-1
| |
| Wiring Diagram 480V Reactor MOV BD 2A Single Line
| |
| Rev. 068
| |
| BFN-2-45E751-8
| |
| Wiring Diagram 480V Reactor MOV BD 2D Single Line
| |
| Rev. 2
| |
| BFN-2-47E812-1-CC
| |
| Flow Diagram, High Pressure Coolant Injection System
| |
| Rev. 77
| |
| BFN-3-47E812-1-CC,
| |
| Flow Diagram, High Pressure Coolant Injection System
| |
| Rev. 73
| |
| Engineering
| |
| Changes
| |
| DCN 72338-03
| |
| Replacement of 4160V/480V Emergency Shutdown
| |
| Board 2A & 2B Transformer
| |
| EC 71425
| |
| Upgrade Unit 1/2 DG Fuel Oil Piping Configuration
| |
| Rev. A
| |
| Miscellaneous
| |
| System Health Report Scorecard for RHRSW and
| |
| EECW (April 2020-September 2020)
| |
|
| |
|
| System Health Report Scorecard for RHRSW and
| | 14. Copy of Technical Specification(s) |
| EECW (October 2020-March 2021)
| |
|
| |
|
| Vendor Letter, Instructions for Changing Assembly of
| | 15. Copy of Technical Specifications Bases |
| DSMM40A Reducer
| |
| dated
| |
| 03/12/02
| |
| System Health Report Scorecard for RHRSW and
| |
| EECW (October 2019-March 2020)
| |
| 0-SI-4.5.C.1(A3-COMP)
| |
| RHRSW Pump A3 IST Comprehensive Pump Test
| |
| Rev. 16
| |
| 0-TI-444
| |
| Augmented Inservice Testing Program
| |
| Rev. 12
| |
| 0-TI-641
| |
| Time Critical Operator Actions
| |
| Rev. 0
| |
| 0048-0051-LTR-002
| |
| BFN HPCI System Waterhammer Evaluation
| |
| Rev. 0
| |
| 0048-0065-RPT-001
| |
| HPCI and RCIC Systems Overpressure Transient
| |
| Technical Review and Development of Mitigation | |
| Options
| |
| Rev. 0
| |
| 70747-71
| |
| 480V RMOV BD 2A/15D ALT FDR from SD BD
| |
| Rev. A
| |
|
| |
|
| Inspection
| | 16. Copy of Technical Requirements Manual(s) |
| Procedure
| |
| Type
| |
| Designation
| |
| Description or Title
| |
| Revision or
| |
| Date
| |
| BFN-1-2020-068-003
| |
| Rev. 0
| |
| BFN-19-918
| |
| U1, U2, and U3 HPCI Gland Seal CKV Addition
| |
| Rev. 1
| |
| BFN-19-918-1
| |
| U1 HPCI Gland Seal CKV Addition
| |
| Rev. 0
| |
| BFN-50-7071
| |
| Design Criteria - Reactor Core Isolation Cooling System
| |
| Rev. 23
| |
| BFN-50-7200C
| |
| Design Basis Document for the 250V DC Power
| |
| Distribution System
| |
| Rev. 8
| |
| BFN-50-720D, 480V
| |
| Auxiliary System
| |
| 480V Auxiliary System
| |
| Rev. 12
| |
| BFN-VTD-D088-0010
| |
| Installation, Operation and Maintenance for Delroyd
| |
| Double Worm Gear Speed Reducers
| |
| Rev. 2
| |
| BFN-VTD-G080-1440
| |
| Vendor Document - Instructions Installation and
| |
| Maintenance of 7700 Line Motor Control Center
| |
| Rev. 2
| |
| BFN-VTD-K143-0020
| |
| Installation and Maintenance Instructions for Kinney
| |
| Automatic Self-Cleaning Strainers Model AV Series
| |
| Rev. 8
| |
| BFN-VTD-K143-0040
| |
| Preventative Maintenance Instructions for S.P. Kinney
| |
| Strainers
| |
| Rev. 0
| |
| BFN-VTD-K143-0050
| |
| Instruction Manual for S.P. Kinney Model AV Series
| |
| Motorized Automatic Self-Cleaning Strainers
| |
| Rev. 0
| |
| BFPER971270
| |
| BF response to NRC IN 91-50 Supplement 1
| |
| Rev. 0
| |
| DCN 69466A
| |
| Replace CS and RHR Room Cooler Fan Motors, Fans,
| |
| and Shafts
| |
| Rev. A
| |
| DCN 70747A
| |
| 50.59 Evaluation
| |
| Rev. 0
| |
| DCN 71376
| |
| Increase Rated Speed of RCIC Pump/Turbine to 4650
| |
| RPM
| |
| Rev. A
| |
| EDC 50911
| |
| Option for Rotating EECW Strainer Gear Reducer 180
| |
| Degrees
| |
| Rev. B
| |
| Fire Protection
| |
| Impairment Permit
| |
| (FPIP) # 21-90 - Unit 3 | |
| Reactor Building
| |
| Elevation 621/638
| |
|
| |
|
| Fire Protection
| | 17. Copy of the Quality Assurance Program Manual |
| Impairment Permit
| |
| (FPIP) # 21-91 - Unit 2
| |
|
| |
|
| Inspection
| | 18. Copy of Corrective Action Program Procedure(s) |
| Procedure
| |
| Type
| |
| Designation
| |
| Description or Title
| |
| Revision or
| |
| Date
| |
| Reactor Building
| |
| Elevation 621/638
| |
| General Design Criteria
| |
| Document No. BN-50-
| |
| 7082
| |
| Standby Diesel Generator
| |
| Rev. 29
| |
| OPL171.051
| |
| Emergency Equipment Cooling Water
| |
| Rev. 9U1
| |
| PMCR 1189814
| |
| Perform 4 Year Inspection of Stand-by Diesel Engine "C"
| |
| PMCR 1189815
| |
| Perform 12-Year Inspection of Standby Diesel "C"
| |
| Engine "C"
| |
| PO 2740686
| |
| Spare Part, Engine, QA1
| |
| dated
| |
| 01/19/17
| |
| Procedures
| |
| 0-ARP-25-41C
| |
| Panel 25-41, 0-XA-55-41C
| |
| Rev. 16
| |
| 0-FSS-001
| |
| Fire Safe Shutdown
| |
| Rev. 5
| |
| 0-FSS-2-2
| |
| U-2, RB EL 519', from R14 to a Line 10' West of R11
| |
| Rev. 8
| |
| 0-FSS-2-3
| |
| U-2, RB EL593 North of Column Line R
| |
| Rev. 13
| |
| 0-GOI-300-1/ATT-12
| |
| Outside Operator Round Log
| |
| Rev. 264
| |
| 0-OI-57B
| |
| 480V/240V AC Electrical System
| |
| Rev. 199
| |
| 0-OI-57D
| |
| DC Electrical System
| |
| Rev. 179
| |
| 0-OI-67
| |
| Emergency Operating Cooling Water System
| |
| Rev. 126
| |
| 0-OI-82
| |
| Standby Diesel Generator System
| |
| Rev. 174
| |
| 0-SI-4.5.C.1(A3)
| |
| RHRSW Pump A3 IST Group A Quarterly Pump Test
| |
| Rev. 19
| |
| 0-SR-3.4.3.1.A
| |
| Bench Test Relief Valves - As Left
| |
| Rev. 6
| |
| 0-TI-346
| |
| Maintenance Rule Performance Indicator Monitoring,
| |
| Trending, and Reporting - 10CFR50.65
| |
| Rev. 54
| |
| 0-TI-362
| |
| Inservice Testing Program
| |
| Rev. 59
| |
| 0-TI-636RLY
| |
| Relay Testing and Maintenance Instruction
| |
| Rev. 2
| |
| 0-TI-641
| |
| Time Critical Operator Actions
| |
| Rev. 0
| |
| 1-ARP-9-8C
| |
| Panel 1-9-8, 1-XA-55-8C
| |
| Rev. 17
| |
| 1/2-ARP-9-23C
| |
| Panel 0-9-23-8, 0-XA-55-23C
| |
| Rev. 35
| |
| 2-SR-3.3.5.1.3(E)
| |
| HPCI Suppression Chamber High Level Calibration and
| |
| Functional Test
| |
| Rev. 21
| |
| 2-SR-3.3.5.1.6(ADS B)
| |
| ADS Logic System Functional Test - Bus B Time Delay
| |
| Relay Calibration and Bus Power Monitor Test
| |
| Rev. 22
| |
|
| |
|
| Inspection
| | 19. Copy of Operability Determination Procedure(s) |
| Procedure
| |
| Type
| |
| Designation
| |
| Description or Title
| |
| Revision or
| |
| Date
| |
| 2-SR-3.5.3.3
| |
| RCIC System Rated Flow at Normal Operating Pressure
| |
| dated
| |
| 01/04/21
| |
| 2-SR-3.5.3.3
| |
| RCIC System Rated Flow at Normal Operating Pressure
| |
| dated
| |
| 10/05/09
| |
| 2-SR-3.5.3.3(COMP)
| |
| RCIC Comprehensive Pump Test
| |
| dated
| |
| 10/10/20
| |
| 2-SR-3.5.3.4
| |
| RCIC System Rated Flow at Low RPV Pressure
| |
| Rev. 26
| |
| ADS Logic System
| |
| Functional Test - Bus B
| |
| Time Delay Relay
| |
| Calibration and Bus
| |
| Power Monitor Test
| |
| Rev. 17
| |
| ECI-0-000-BRK008
| |
| Testing and Troubleshooting of Molded Case Circuit
| |
| Breakers and Motor Starter Overload Relays
| |
| dated
| |
| 03/21/15
| |
| EII-0-000-TCC106
| |
| Troubleshooting, Documentation and Configuration
| |
| Control of Electrical Activities
| |
| dated
| |
| 03/26/15
| |
| EPI-0-000-MCC001
| |
| Maintenance and Inspection of 480VAC and 250VDC
| |
| Motor Control Centers
| |
| dated
| |
| 03/20/15
| |
| EPI-0-281-RLY001
| |
| Relay Calibration and Functional Tests on 250V DC
| |
| Reactor MOV Boards
| |
| Rev. 13
| |
| MAI-3.4A
| |
| Internal Conduit Seals
| |
| Rev. 17
| |
| MCI-0-001-VLV002
| |
| Main Steam Relief Valves Target Rock Model 7567
| |
| Disassembly, Inspection, Repair and Reassembly
| |
| Rev. 54
| |
| MSI-0-071-GOV001
| |
| Reactor Core Isolation Cooling (RCIC) Overspeed Trip
| |
| Test
| |
| Rev. 36
| |
| MSI-2-001-TST002
| |
| Testing of Air Supply System (Drywell Side-East) for
| |
| Main Steam Isolation Valves and Automatic
| |
| Depressurization System Main Steam Relief Valves
| |
| Rev. 14
| |
| MSI-2-001-TST003
| |
| Testing Air Supply System (Drywell Side-West) for Main
| |
| Steam Isolation Valves and Automatic Depressurization
| |
| System Main Steam Relief Valves
| |
| Rev. 12
| |
| NEDP-10
| |
| Rev. 25
| |
| NEDP-2
| |
| Design Calculation Process Control
| |
| Rev. 25
| |
| NEDP-22
| |
| Operability Determinations and Functional Evaluations
| |
| Rev. 21
| |
|
| |
|
| Inspection
| | 20. List of motor operated valves and air operated valves in the valve program, and their associated design margin and risk ranking |
| Procedure
| |
| Type
| |
| Designation
| |
| Description or Title
| |
| Revision or
| |
| Date
| |
| NPG-SPP-09.3
| |
| Plant Modifications and Engineering Change Control
| |
| Rev. 35
| |
| NPG-SPP-22.206
| |
| Verification Program
| |
| Rev. 7
| |
| Work Orders
| |
| 116092256
| |
|
| |
|
| 117821889
| | 21. Primary AC and DC calculations for safety-related buses |
|
| |
|
| 117821892
| | 22. One-line diagram of electrical plant (Electronic only) |
|
| |
|
| 117821901
| | 23. Index and legend for electrical plant one-line diagrams |
|
| |
|
| 117821908
| | 24. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic) |
|
| |
|
| 118569627
| | 25. Index and legend for P&IDs |
|
| |
|
| 118800332
| | 26. Index (procedure number, title, and current revision) of station Emergency Operating Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures |
|
| |
|
| 119041410
| | 27. Copies of corrective action documents generated from previous CDBI |
| 21166362
| |
| 20898561
| |
| 118571292
| |
| 118571299
| |
| 20561899
| |
| 119698618
| |
| 20136130
| |
| 21260764
| |
| 118571303
| |
| 119698622
| |
| 20136126
| |
| 119189075
| |
| 119189052
| |
| 119189076
| |
| 118323602
| |
| 115753060
| |
| 01-012729-000
| |
| 01-012729-001
| |
| 01-012729-002
| |
| 01-012729-003
| |
| 01-012730-000
| |
| 01-012730-001
| |
| 01-012730-002
| |
| 21325467
| |
|
| |
|
| Inspection
| | 28. Copy of any self-assessments performed, and corrective action documents generated, in preparation for current DBAI |
| Procedure
| |
| Type
| |
| Designation
| |
| Description or Title
| |
| Revision or
| |
| Date
| |
| 21331211
| |
| 21385840
| |
| 21390551
| |
| 21504079
| |
| 21504079
| |
| 21785957
| |
| 21808045
| |
| 119585512
| |
|
| |
|
| 119639739
| | 29. Contact information for a person to discuss PSA information prior to and during the information-gathering trip (Name, title, phone number, and e-mail address) |
| }} | | }} |
|
|---|
Category:Inspection Plan
MONTHYEARML24262A1502024-09-24024 September 2024
Requalification Program Inspection - Browns Ferry Nuclear Plant
IR 05000259/20240052024-08-26026 August 2024
Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005
ML24225A1682024-08-16016 August 2024
– Notification of Inspection and Request
ML24087A1822024-03-28028 March 2024
Notification of Target Set Inspection and Request for Information NRC Inspection Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403
ML24052A1472024-02-28028 February 2024
Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023006, 05000260/2023006 and 05000296/2023006
IR 05000259/20230052023-08-29029 August 2023
Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005
IR 05000259/20220062023-03-0101 March 2023
Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 Report 05000259/2022006, 05000260/2022006 and 05000296/2022006
ML23020A0602023-01-20020 January 2023
Long Term Steam Dryer Inspection Plan
IR 05000259/20220052022-08-30030 August 2022
Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 Report 05000259/2022005, 05000260/2022005 and 05000296/2022005
ML22210A1342022-07-20020 July 2022
Requalification Inspection Notification Letter
ML22174A2722022-06-24024 June 2022
Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection
IR 05000259/20224012022-03-0808 March 2022
Information Request for the Cyber-Security Baseline Inspection Notification to Perform Inspection 05000259/2022401; 05000260/2022401; 05000296/2022401
ML22091A1942022-03-0808 March 2022
2022 BFN POV Inspection Information Request
IR 05000259/20210062022-03-0202 March 2022
Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 (Report No. 05000259/2021006, 05000260/2021006 and 05000296/2021006
ML22025A4132022-01-25025 January 2022
RP Inspection Doc Request
ML22018A0292022-01-18018 January 2022
Region 2 RFI - 2022 Program Inspections
ML21343A4232021-12-0909 December 2021
Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000259/2022010, 05000260/2022010, and 05000296/2022010) and Request for Information (RFI)
IR 05000259/20210052021-08-23023 August 2021
Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2, and 3- Report Nos. 05000259/2021005, 05000260/2021005 and 5000296/2021005
IR 05000259/20200062021-03-0303 March 2021
Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2020006, 05000260/2020006 and 05000296/2020006
IR 05000259/20210102021-02-16016 February 2021
Notification of Browns Ferry Nuclear Power Plant Design Bases Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000259/2021010, 05000260/2021010, and 05000296/2021010
ML20338A3682020-12-0303 December 2020
Notification of Inspection and Request for Information
ML20266G4472020-09-22022 September 2020
Notification of Inspection and Request for Information
IR 05000259/20200052020-08-18018 August 2020
Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2020005, 05000260/2020005, and 05000296/2020005
ML20191A2232020-07-0909 July 2020
Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection
IR 05000259/20190062020-03-0303 March 2020
Annual Assessment Letter for Browns Ferry Nuclear Plant Units 1,2,and 3 - NRC Report 05000259/2019006, 05000260/2019006, and 05000296/2019006
ML19108A1682019-04-18018 April 2019
EP Exercise Inspection RFI
IR 05000259/20180062019-03-0404 March 2019
Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2018006, 05000260/2018006 and 05000328/2018006
ML19030A6712019-01-25025 January 2019
U2 ISI RFI
ML19024A4112019-01-24024 January 2019
Transmittal of RP Baseline Inspection Document Request 2019
ML18264A2052018-09-21021 September 2018
U1 ISI Emailed RFI Notification
ML18059A1052018-02-28028 February 2018
EOC Assessment Letter
IR 05000259/20180102018-01-29029 January 2018
Notification of Browns Ferry Nuclear Plant Design Bases Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000259/2018010, 05000260/2018010, and 05000296/2018010
ML18029A2552018-01-29029 January 2018
U3 RFI Email Request
ML17236A1972017-08-24024 August 2017
Updated Inspection Plan
ML17156A1612017-06-0202 June 2017
Notification of Inspection and Request for Information
IR 05000259/20160062017-03-0101 March 2017
Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2, and 3 (Report 05000259/2016006, 05000260/2016006 and 05000296/2016006)
IR 05000259/20160052016-08-31031 August 2016
Mid-Cycle Assessment Letter for Browns Ferry Nuclear Plant Units 1, 2 and 3, NRC Inspection Reports 05000259/2016005, 05000260/2016005 and 05000296/2016005
ML16243A2242016-08-30030 August 2016
Notification of Inspection and Request for Information
ML16120A1182016-04-27027 April 2016
Notification of Conduct of a Triennial Fire Protection Baseline Inspection - U.S. Nuclear Regulatory Commission Inspection Report Nos. 05000259/2016011, 05000260/2016011 and 05000296/2016011
IR 05000259/20150062016-03-0202 March 2016
Annual Assessment Letter for Browns Ferry Nuclear Plant Units 1, 2 and 3 � NRC Inspection Reports 05000259/2015006, 05000260/2015006 and 05000296/2015006
ML16013A0812016-01-12012 January 2016
Notification of Inspection and Request for Information
ML15348A1802015-12-14014 December 2015
Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection
IR 05000259/20150052015-09-0101 September 2015
Mid-Cycle Assessment Letter for the Browns Ferry Nuclear Plant Units 1, 2 and 3, NRC Inspection Report 005000259/2015005, 005000260/2015005, and 005000296/2015005
IR 05000259/20140012015-03-0404 March 2015
Annual Assessment Letter for Browns Ferry Nuclear Plant Units 1, 2 and 3 - NRC Inspection Reports 05000259/2014001, 05000260/2014001 and 05000296/2014001
IR 05000259/20140062014-09-0202 September 2014
Mid-Cycle Assessment Letter for Browns Ferry Nuclear Plant Units 1, 2 and 3 (NRC Inspection Reports 05000259/2014006, 05000260/2014006 and 05000296/2014006)
ML14063A1092014-03-0404 March 2014
2013 Annual Assessment Letter for Browns Ferry
ML14031A4122014-01-31031 January 2014
U3 2014002 ISI RFI Final - Copy
ML14028A1912014-01-28028 January 2014
Notification of Inspection and Request for Information
ML13353A5852013-12-19019 December 2013
PIR Notification Letter 2014
ML13246A1842013-09-0303 September 2013
Mid Cycle Assessment Letter
2024-09-24
[Table view]
Category:Letter
MONTHYEARIR 05000259/20240112024-12-26026 December 2024
Biennial Problem Identification and Resolution Inspection Report 05000259/2024011, 05000260/2024011, and 05000296/2024011
ML24354A2092024-12-19019 December 2024
American Society of Mechanical Engineers, Section XI, Third 10 Year Inspection Interval, Inspection Service, System Procedure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear
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Brown Ferry Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2 and Watts Bar Plant, Units 1 & 2 - Triennial Decommission Funding Plans for Independent Spent Fuel Storage Installations
CNL-24-082, Central Emergency Control Center Emergency Plan Implementing Procedure Revision2024-12-17017 December 2024
Central Emergency Control Center Emergency Plan Implementing Procedure Revision
CNL-24-081, Application for Subsequent Renewed Operating Licenses, Third Safety Supplement2024-12-17017 December 2024
Application for Subsequent Renewed Operating Licenses, Third Safety Supplement
CNL-24-083, Alabama Department of Environmental Management Letter2024-12-10010 December 2024
Alabama Department of Environmental Management Letter
CNL-24-049, Brows Ferry Nuclear Plant, Units 1, 2 and 3 - License Amendment Request for Adoption of TSTF-576 to Revise Safety/Relief Valve Requirements2024-12-0909 December 2024
Brows Ferry Nuclear Plant, Units 1, 2 and 3 - License Amendment Request for Adoption of TSTF-576 to Revise Safety/Relief Valve Requirements
05000296/LER-2024-004, Reactor Coolant System Pressure Boundary Leakage Identified from Recirculation System Small Bore Piping2024-12-0404 December 2024
Reactor Coolant System Pressure Boundary Leakage Identified from Recirculation System Small Bore Piping
05000260/LER-2024-002-01, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-11-25025 November 2024
High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation
IR 05000260/20240912024-11-21021 November 2024
Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter NRC Inspection Report 05000260/2024091
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Notification of Licensed Operator Initial Examination 05000259/2025301, 05000260/2025301, 05000296/2025301
IR 05000259/20240102024-11-12012 November 2024
Design Basis Assurance Inspection Program Inspection Report 05000259/2024010 and 05000260/2024010 and 05000296/2024010
IR 05000259/20240032024-11-0404 November 2024
Integrated Inspection Report 05000259/2024003 and 05000260/2024003 and 05000296/2024003
CNL-24-043, Application for Subsequent Renewed Operating Licenses, Second Safety Supplement2024-11-0101 November 2024
Application for Subsequent Renewed Operating Licenses, Second Safety Supplement
ML24305A1692024-10-31031 October 2024
Site Emergency Plan Implementing Procedure Revision
05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-29029 October 2024
Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators
05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-10-28028 October 2024
Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure
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Response to Apparent Violation in NRC Inspection Report 05000260/2024090, EA-24-075
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Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry
CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
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Ahc 24-1578 Environmental Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Subsequent License Renewal Application Limestone County
CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024
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Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075
CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024
Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description
ML24262A1502024-09-24024 September 2024
Requalification Program Inspection - Browns Ferry Nuclear Plant
ML24262A0602024-09-23023 September 2024
Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan
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Site Emergency Plan Implementing Procedure Revision
CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024
Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
IR 05000260/20240902024-09-17017 September 2024
NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1
CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024
Cycle 16 Reload Analysis Report
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Core Operating Limits Report for Cycle 16 Operation, Revision 0
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Full Audit Plan
IR 05000259/20244042024-09-0303 September 2024
Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter
IR 05000259/20240052024-08-26026 August 2024
Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005
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– Notification of Inspection and Request
ML24219A0272024-08-0606 August 2024
Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations
IR 05000259/20244022024-08-0606 August 2024
Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402
IR 05000259/20240022024-08-0202 August 2024
Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002
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Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2)
ML24172A1342024-07-15015 July 2024
Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter
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Inoperability of Unit 3 Diesel Generator Due to Relay Failure
ML24184A1142024-07-0202 July 2024
Site Emergency Plan Implementing Procedure Revision
ML24183A3842024-07-0101 July 2024
Registration of Use of Cask to Store Spent Fuel (MPC-364, -365)
ML24179A0282024-06-26026 June 2024
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Reactor Scram Due to Generator Step-Up Transformer Failure
ML24175A0042024-06-23023 June 2024
Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System
ML24176A1132024-06-23023 June 2024
American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper
ML24089A1152024-06-21021 June 2024
Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2)
2024-09-03
[Table view] |
Text
February 16, 2021
SUBJECT:
NOTIFICATION OF BROWNS FERRY NUCLEAR POWER PLANT DESIGN BASES ASSURANCE INSPECTION - U.S. NUCLEAR REGULATORY COMMISSION INSPECTION REPORT 05000259/2021010, 05000260/2021010, AND 05000296/2021010
Dear Mr. Barstow:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a Design Bases Assurance Inspection (DBAI) at your Browns Ferry Nuclear Power Plant during the weeks of May 17 - 21, and June 7 - 11, 2021.
Mr. Marcus Riley, a reactor inspector from the NRCs Region II office, will lead the inspection team. The inspection will be conducted in accordance with Inspection Procedure 71111.21M, Design Bases Assurance Inspection (Teams), dated December 8, 2016 (ADAMS ML16238A320).
The inspection will evaluate the capability of components that have been modified and risk-significant/low-margin components to function as designed and to support proper system operation. The inspection will also include a review of selected operator actions, operating experience, and modifications.
During a telephone conversation on February 11, 2021, with Mr. Denzel Housley, we confirmed arrangements for an information-gathering site visit and the two-week onsite inspection. The schedule is as follows:
- Information-gathering visit: Week of April 26 - 30, 2021
Onsite weeks: Weeks of May 17 - 21, and June 7 - 11, 2021
The purpose of the information-gathering visit is to meet with members of your staff to identify components that have been modified, risk-significant components, and operator actions.
Information and documentation needed to support the inspection will also be identified.
Mr. Andy Rosebrook, a Region II Senior Risk Analyst, will support Mr. Riley during the information-gathering visit to review probabilistic risk assessment data and identify components to be examined during the inspection. Additionally, during the onsite weeks, time will be needed on the plant-referenced simulator in order to facilitate the development of operator action-based scenarios. The enclosure lists documents that will be needed prior to the information-gathering visit.
Please provide the referenced information to the Region II Office by Friday, April 16, 2021.
Additional documents will be requested following the information-gathering visit. The inspectors will try to minimize your administrative burden by specifically identifying only those documents required for inspection preparation. The additional information will be needed in the Region II office by Friday, May 7, 2021, to support the inspection teams preparation week. During the information-gathering trip, Mr. Riley will also discuss the following inspection support administrative details, as applicable: (1) availability of knowledgeable plant engineering and licensing personnel to serve as points of contact during the inspection; (2) method of tracking inspector requests during the inspection; (3) licensee computer access; (4) working space; (5)
arrangements for site access; and (6) other applicable information.
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.
Thank you for your cooperation in this matter. If you have any questions, regarding the information requested or the inspection, please contact Mr. Riley at 404-997-4888 or contact me at 404-997-4506.
Sincerely,
/RA/
James Baptist, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-259, 50-260, 50-296 License Nos.: DPR-33, DPR-52, DPR-68
Enclosure:
Notification of Browns Ferry Nuclear Power Plant, Design Bases Assurance Inspection (Teams)
cc: Distribution via Listserv
ML21047A473 X
SUNSI Review
X Non-Sensitive
Sensitive
X Publicly Available
Non-Publicly Available
OFFICE RII/DRS RII/DRS
NAME M. Riley J. Baptist
DATE 02/12/2021 02/12/2021
Enclosure INFORMATION REQUEST FOR BROWNS FERRY NUCLEAR POWER PLANT DESIGN BASES ASSURANCE INSPECTION (TEAMS)
Please provide the information electronically in.pdf files, Excel, or other searchable format on CDROM (or FTP site, SharePoint, etc.). The CDROM (or website) should be indexed and hyperlinked to facilitate ease of use. The requested items below, identified with an asterisk (*),
should have a date range from January 1, 2018, until present.
1.
- List and brief description of permanent and field work completed plant modifications including permanent plant changes, design changes, set point changes, procedure changes, equivalency evaluations, suitability analyses, calculations, and commercial grade dedications. Include an index of systems (system numbers/designators and corresponding names), the safety classification for each modification, and type of modification.
2.
From your most recent probabilistic safety analysis (PSA) excluding external events and fires:
a. Two risk rankings of components from your site-specific PSA: one sorted by Risk Achievement Worth (RAW), and the other sorted by Birnbaum Importance
b. A list of the top 500 cut-sets
c. A list of the top 500 LERF contributors
3.
From your most recent PSA including external events and fires:
a. Two risk rankings of components from your site-specific PSA: one sorted by RAW, and the other sorted by Birnbaum Importance
b. A list of the top 500 cut-sets
4.
Risk ranking of operator actions from your site-specific PSA sorted by RAW and human reliability worksheets for these items
5.
List of time-critical operator actions with a brief description of each action
6.
- List of components with low-design margins (i.e., pumps closest to the design limit for flow or pressure, diesel generator close to design-required output, heat exchangers close to rated design heat removal, and motor-operated valve risk-margin rankings, etc.) and associated evaluations or calculations
7.
- List and brief description of Root Cause Evaluations performed 8.
- List and brief description of common-cause component failures that have occurred
9.
10. *List and reason for equipment that has been classified in maintenance rule (a)(1) status
11. *List of equipment on the sites Station Equipment Reliability Issues List, including a description of the reason(s) why each component is on that list, and summaries (if available) of your plans to address the issue(s) along with dates added or removed from the issues list
12. List of current operator work arounds/burdens
13. Copy of Updated Final Safety Analysis Report
14. Copy of Technical Specification(s)
15. Copy of Technical Specifications Bases
16. Copy of Technical Requirements Manual(s)
17. Copy of the Quality Assurance Program Manual
18. Copy of Corrective Action Program Procedure(s)
19. Copy of Operability Determination Procedure(s)
20. List of motor operated valves and air operated valves in the valve program, and their associated design margin and risk ranking
21. Primary AC and DC calculations for safety-related buses
22. One-line diagram of electrical plant (Electronic only)
23. Index and legend for electrical plant one-line diagrams
24. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic)
25. Index and legend for P&IDs
26. Index (procedure number, title, and current revision) of station Emergency Operating Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures
27. Copies of corrective action documents generated from previous CDBI
28. Copy of any self-assessments performed, and corrective action documents generated, in preparation for current DBAI
29. Contact information for a person to discuss PSA information prior to and during the information-gathering trip (Name, title, phone number, and e-mail address)
