IR 05000259/2021010: Difference between revisions

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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.
 
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,
Sincerely,
/RA/
/RA/  
James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 05000259 and 05000260 and 05000296 License Nos. DPR-33 and DPR-52 and DPR-68
 
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.
* List and brief description of Operability Determinations and Functionality Assessments
 
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


===Enclosure:===
13. Copy of Updated Final Safety Analysis Report
As stated


==Inspection Report==
14. Copy of Technical Specification(s)
Docket Numbers: 05000259, 05000260 and 05000296 License Numbers: DPR-33, DPR-52 and DPR-68 Report Numbers: 05000259/2021010, 05000260/2021010 and 05000296/2021010 Enterprise Identifier: I-2021-010-0038 Licensee: Tennessee Valley Authority Facility: Browns Ferry Nuclear Plant Location: Athens, AL Inspection Dates: May 17, 2021 to June 11, 2021 Inspectors: C. Baron, Contractor D. Bollock, Senior Reactor Operations Engineer W. Deschaine, Senior Resident Inspector S. Kobylarz, Contractor R. Patterson, Senior Reactor Inspector J. Winslow, Reactor Systems Engineer Approved By: James B. Baptist, Chief Engineering Branch 1 Division of Reactor Safety Enclosure


=SUMMARY=
15. Copy of Technical Specifications Bases
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===
16. Copy of Technical Requirements Manual(s)


No findings or violations of more than minor significance were identified.
17. Copy of the Quality Assurance Program Manual


===Additional Tracking Items===
18. Copy of Corrective Action Program Procedure(s)
None.


=INSPECTION SCOPES=
19. Copy of Operability Determination Procedure(s)


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.
20. List of motor operated valves and air operated valves in the valve program, and their associated design margin and risk ranking


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.
21. Primary AC and DC calculations for safety-related buses


==REACTOR SAFETY==
22. One-line diagram of electrical plant (Electronic only)


===71111.21M - Design Bases Assurance Inspection (Teams) The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:
23. Index and legend for electrical plant one-line diagrams
Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02) (4 Samples)
: (1) 250V DC Reactor Motor Operated Valve (RMOV) Board 2B
* 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
* 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) ===
{{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)===
24. Piping and instrumentation diagrams (P&IDs) for safety-related systems (Electronic)  
: (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)===
25. Index and legend for P&IDs
: (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==
26. Index (procedure number, title, and current revision) of station Emergency Operating Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures
No findings were identified.


==EXIT MEETINGS AND DEBRIEFS==
27. Copies of corrective action documents generated from previous CDBI
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=
28. Copy of any self-assessments performed, and corrective action documents generated, in preparation for current DBAI


Inspection Type        Designation      Description or Title                                    Revision or
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)
Procedure                                                                                      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  Rev. 1
Strainer
CDQ-0067894672  Evaluation and Review of Small Bore Unit 0 Piping and  Rev. 12
Supports within the Scope of the System 067 Safe
Shutdown Boundary
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                Rev. 2
Components for the Affects of Tornadic Wind- RHRSW
Pump
CDQ0999910005    Evaluation of Seismic- Induced Spray Hazards at BFN,    Rev. 3
Unit 2 and Common
CDQ107320021062  Small Bore Piping and Supports Program System          Rev. 6
Calculation for Seismic Class 1 HPCI System (73) Piping
CDQ107320031063  Pipe Stress Analysis of Stress Problem N1-173-67R      Rev. 1
EDQ0057920034    4.16KV and 480V Busload, Voltage Drop and Short        Rev. 92
Circuit Calculation
EDQ024820020042  250V DC Unit Battery Load Study                        Rev. 91
EDQ2000870054    Control Circuit Voltage Drop Calculations - 250V DC    Rev. 43
circuits
EDQ2000870550    Cable and Bus Protection/Breaker/Fuse Coordination for  Rev. 54
250V DC System
EDQ2092900118    Setpoint and Scaling Calculation for Neutron Monitoring Rev. 37
System & Recirculation Flaw Loops
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-            MOV 0-FCV-067-0001/0005/0008/0011, Operator            Rev. 1
0000672019000460 Requirements and Capabilities
MDQ-0067890059  Analytical Limits for the EECW Strainers and Strainer  Rev. 2
Inspection Type              Designation        Description or Title                                  Revision or
Procedure                                                                                              Date
Drain Valves Start/Stop Controls
MDQ0000712012000031 RCIC Pump NPSHa and System Hydraulic Analysis        Rev. 3
                                                (Pump Water Suction and Discharge)
MDQ0000732012000062 Calculation of Effects of Gas Accumulation in ECCS    Rev. 0
Piping
MDQ0032870288      Control Air Volume and Wall Thickness of Accumulators Rev. 14
MDQ0071910235      Reactor Core Isolation Cooling System Design          Rev. 12
Pressure/Temperature
MDQ099920040034    Setpoint Controls Parameters Review Calculation for  Rev. 17
BFN Category 2 Air Operated Valves (AOVs)
MDQ099920040040    HPCI and RCIC Test Requirements                      Rev. 11
NDN00099920070032  BFN Probablistic Risk Assessment - Human Reliability  Rev. 8
Analysis
Corrective Action 0044691
Documents        0128951
0175232
200183
1648705
1649288
1649610
1652318
1369055
1406271
1499731
1500527
1557241
1606454
1607278
1613986
1614688
1617438
27370
1638651
1655591
Inspection Type              Designation Description or Title                                Revision or
Procedure                                                                                    Date
1656541
1656544
1658162
1658186
1658998
1664478
1665909
1676979
1687954
1688353
1695185
201387
21012
1434874
1435350
1613271
Corrective Action 1695185    A3 RHRSW Lube Oil Strainer Sight Glass
Documents        1695266    Control of HPCI and RCIC System Flow Controller
Resulting from                Settings
Inspection        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 Type    Designation  Description or Title                                    Revision or
Procedure                                                                                  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      Rev. 5
Seal Tabular Drawings General Notes and Legend
0-47E840-3    Flow Diagram, Fuel Oil System                            Rev. 27
0-731E700    One Line Diagram of DC & Instrument Control AC          Rev. 8
Systems
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      Rev. 1
Seal Location Drawings Plan View Area I
2-47W2392-708 Fire Protection - 10 CFR 50 Appendix R Penetration      Rev. 1
Seal Location Drawings EL 639
Inspection Type          Designation          Description or Title                                Revision or
Procedure                                                                                          Date
2-47W2392-716        Fire Protection - 10 CFR 50 Appendix R Penetration  Rev. 3
Seal Tabular Drawings EL 639
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      Rev. 38
Cooling Water
BFN-1-47E610-67-1    Mechanical Control Diagram, Emergency Equipment      Rev. 50
Cooling Water
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  DCN 72338-03          Replacement of 4160V/480V Emergency Shutdown
Changes                            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
EECW (October 2020-March 2021)
Vendor Letter, Instructions for Changing Assembly of dated
DSMM40A Reducer                                      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        Rev. 0
Technical Review and Development of Mitigation
Options
70747-71              480V RMOV BD 2A/15D ALT FDR from SD BD              Rev. A
Inspection Type Designation            Description or Title                                    Revision or
Procedure                                                                                      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            Rev. 8
Distribution System
BFN-50-720D, 480V      480V Auxiliary System                                  Rev. 12
Auxiliary System
BFN-VTD-D088-0010      Installation, Operation and Maintenance for Delroyd    Rev. 2
Double Worm Gear Speed Reducers
BFN-VTD-G080-1440      Vendor Document - Instructions Installation and        Rev. 2
Maintenance of 7700 Line Motor Control Center
BFN-VTD-K143-0020        Installation and Maintenance Instructions for Kinney  Rev. 8
Automatic Self-Cleaning Strainers Model AV Series
BFN-VTD-K143-0040      Preventative Maintenance Instructions for S.P. Kinney  Rev. 0
Strainers
BFN-VTD-K143-0050      Instruction Manual for S.P. Kinney Model AV Series      Rev. 0
Motorized Automatic Self-Cleaning Strainers
BFPER971270            BF response to NRC IN 91-50 Supplement 1                Rev. 0
DCN 69466A              Replace CS and RHR Room Cooler Fan Motors, Fans,        Rev. A
and Shafts
DCN 70747A              50.59 Evaluation                                        Rev. 0
DCN 71376              Increase Rated Speed of RCIC Pump/Turbine to 4650      Rev. A
RPM
EDC 50911              Option for Rotating EECW Strainer Gear Reducer 180      Rev. B
Degrees
Fire Protection
Impairment Permit
                (FPIP) # 21-90 - Unit 3
Reactor Building
Elevation 621/638
Fire Protection
Impairment Permit
                (FPIP) # 21-91 - Unit 2
Inspection Type      Designation            Description or Title                                    Revision or
Procedure                                                                                            Date
Reactor Building
Elevation 621/638
General Design Criteria Standby Diesel Generator                                Rev. 29
Document No. BN-50-
7082
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,      Rev. 54
Trending, and Reporting - 10CFR50.65
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    Rev. 21
Functional Test
2-SR-3.3.5.1.6(ADS B)  ADS Logic System Functional Test - Bus B Time Delay    Rev. 22
Relay Calibration and Bus Power Monitor Test
Inspection Type Designation            Description or Title                                  Revision or
Procedure                                                                                      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        Rev. 17
Functional Test - Bus B
Time Delay Relay
Calibration and Bus
Power Monitor Test
ECI-0-000-BRK008        Testing and Troubleshooting of Molded Case Circuit    dated
Breakers and Motor Starter Overload Relays            03/21/15
EII-0-000-TCC106        Troubleshooting, Documentation and Configuration      dated
Control of Electrical Activities                      03/26/15
EPI-0-000-MCC001        Maintenance and Inspection of 480VAC and 250VDC        dated
Motor Control Centers                                  03/20/15
EPI-0-281-RLY001        Relay Calibration and Functional Tests on 250V DC      Rev. 13
Reactor MOV Boards
MAI-3.4A                Internal Conduit Seals                                Rev. 17
MCI-0-001-VLV002        Main Steam Relief Valves Target Rock Model 7567        Rev. 54
Disassembly, Inspection, Repair and Reassembly
MSI-0-071-GOV001        Reactor Core Isolation Cooling (RCIC) Overspeed Trip  Rev. 36
Test
MSI-2-001-TST002        Testing of Air Supply System (Drywell Side-East) for  Rev. 14
Main Steam Isolation Valves and Automatic
Depressurization System Main Steam Relief Valves
MSI-2-001-TST003        Testing Air Supply System (Drywell Side-West) for Main Rev. 12
Steam Isolation Valves and Automatic Depressurization
System Main Steam Relief Valves
NEDP-10                Rev. 25
NEDP-2                  Design Calculation Process Control                    Rev. 25
NEDP-22                Operability Determinations and Functional Evaluations  Rev. 21
Inspection Type        Designation    Description or Title                              Revision or
Procedure                                                                                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
117821892
117821901
117821908
118569627
118800332
119041410
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 Type Designation Description or Title Revision or
Procedure                                        Date
21331211
21385840
21390551
21504079
21504079
21785957
21808045
119585512
119639739
15
}}
}}

Latest revision as of 11:03, 29 November 2024

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
ML21047A473
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 02/16/2021
From: James Baptist
NRC/RGN-II/DRS/EB1
To: Jim Barstow
Tennessee Valley Authority
References
IR 2021010
Download: ML21047A473 (5)
v • d • e


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)

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