IR 05000259/2021004
| ML22031A142 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/31/2022 |
| From: | Tom Stephen Division Reactor Projects II |
| To: | Jim Barstow Tennessee Valley Authority |
| References | |
| IR 2021004 | |
| Download: ML22031A142 (19) | |
Text
January 31, 2022
SUBJECT:
BROWNS FERRY NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000259/2021004, 05000260/2021004 AND 05000296/2021004
Dear Mr. Barstow:
On December 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Browns Ferry Nuclear Plant. On January 26, 2022, the NRC inspectors discussed the results of this inspection with Mr. Daniel Komm and other members of your staff. The results of this inspection are documented in the enclosed report.
One Severity Level IV violation without an associated finding is documented in this report. We are treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy.
A licensee-identified violation which was determined to be of very low safety significance is documented in this report. We are treating this violation as a non-cited violation (NCV)
consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violations or the significance or severity of the violations documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC Resident Inspector at Browns Ferry Nuclear Plant.
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.
Sincerely,
/RA/
Thomas A. Stephen, Chief Reactor Projects Branch 5 Division of Reactor Projects
Docket Nos. 05000259, 05000260 and 05000296 License Nos. DPR-33, DPR-52, and DPR-68
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000259, 05000260 and 05000296
License Numbers:
Report Numbers:
05000259/2021004, 05000260/2021004 and 05000296/2021004
Enterprise Identifier: I-2021-004-0009
Licensee:
Tennessee Valley Authority
Facility:
Browns Ferry Nuclear Plant
Location:
Athens, Alabama
Inspection Dates:
October 01, 2021 to December 31, 2021
Inspectors:
N. Karlovich, Resident Inspector
M. Kirk, Resident Inspector
D. Lanyi, Senior Reactor Operations
J. Montgomery, Senior Reactor Inspector
J. Steward, Senior Resident Inspector
Approved By:
Thomas A. Stephen, Chief
Reactor Projects Branch 5
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated 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. A licensee-identified non-cited violation is documented in report section: 7115
List of Findings and Violations
Browns Ferry Nuclear Plant, Unit 2, Main Steam Relief Valves Lift Settings Outside of Technical Specification Required Setpoints Cornerstone Severity Cross-Cutting Aspect Report Section Not Applicable Severity Level IV NCV 05000260/2021004-01 Open/Closed Not Applicable 71153 A self-revealed Severity Level IV NCV of Technical Specification (TS) 3.4.3 and TS 3.0.4 was identified when the licensee discovered, through as found test results, that five of thirteen Main Steam Relief Valves (MSRVs) that were removed for testing had as found lift settings outside of the +/-3 percent setpoint band required for their operability.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000259,05000260,05 000296/2020-002-00 Standby Gas Treatment System Train B Inoperable Longer Than Allowed by Technical Specifications 71153 Closed LER 05000260/2021-002-00 Browns Ferry Nuclear Plant,
Unit 2, Main Steam Relief Valves Lift Settings Outside of Technical Specification Required Setpoints 71153 Closed LER 05000259,05000260,05 000296/2020-002-01 Standby Gas Treatment Train B Inoperable Longer Than Allowed by Technical Specifications 71153 Closed
PLANT STATUS
Unit 1 began the inspection period at 100 percent rated thermal power (RTP). On December 9, 2021, the Unit performed a planned downpower to 60 percent RTP for planned maintenance and testing, including power suppression testing conducted to identify and isolate a fuel bundle which indicated elevated activity levels representative of a potential fuel defect. Following a preconditioning ramp rate, the Unit returned to RTP on December 14, 2021, where it remained through the end of the inspection period.
Unit 2 began the inspection period at 100 percent RTP. On December 3, 2021, the Unit performed a planned downpower to 70 percent RTP to perform a control rod sequence exchange. Unit 2 returned to RTP on December 4, 2021, where it remained through the end of the inspection period.
Unit 3 began the inspection period at 100 percent RTP. On November 11, 2021, the Unit performed a planned downpower to 70 percent RTP to perform a control rod sequence exchange and other planned maintenance. The unit returned to RTP on November 15, 2021, and operated there until December 3, 2021, when the unit performed a planned downpower to 90 percent RTP to perform a rod pattern adjustment and other planned testing. The Unit was returned to RTP later that same day and continued to operate there until December 15, 2021, when the unit achieved all rods out configuration with maximum core flow. On December 17, 2021, the unit commenced coastdown with the amount of power limited by maximum core flow. The Unit continued to operate in coastdown and operated at 93 percent RTP at the end of the inspection period.
INSPECTION SCOPES
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 performed activities described in IMC 2515, Appendix D, Plant Status, conducted routine reviews using IP 71152, Problem Identification and Resolution, observed risk significant activities, and completed on-site portions of IPs. 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.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the adequacy of the corrective actions associated with the temporary loss of transmission's supervisory control and data acquisition (SCADA)and its impact to overall preparations to protect risk-significant systems from impending severe weather on November 28, 2021.
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding on October 22, 2021.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Units 1 and 2, Main control room air handling unit (AHU) 1A with AHU 1B out of service on October 5, 2021
- (2) Unit 3, Residual heat removal (RHR) system Loop II on October 7, 2021
- (3) Unit 1, Reactor core isolation cooling (RCIC) system with High Pressure Coolant Injection (HPCI) out of service on October 13, 2021
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Units 2 and 3, Fire Area 16-A, Spreading Room B on October 14, 2021
- (2) Unit 1, Fire Area 16-K, Auxiliary Instrument Room #1 on November 4, 2021
- (3) Units 1 and 2, Fire Area 8, Electric board room 2B ('D' 4kV shutdown board) on November 5, 2021
- (4) Units 1 and 2, Fire Area 9, Electric board room 2A ('C' 4kV shutdown board) and 250V battery rooms on November 5, 2021
- (5) Units 1,2 and 3 Fire Area YARD Off Gas Treatment Building, 556 and 538 Elevations on November 8, 2021
- (6) Unit 3, Fire Area 13, Electrical board room 3A on November 9, 2021
- (7) Unit 3, Fire Area 16-A, Control Bay Chiller Room on November 23, 2021
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) Annual Review of Licensee Requalification Examination Results: The licensee completed the annual requalification operating examinations required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), "Requalification Requirements," of the NRC's "Operator's Licenses." During the week of December 13, 2021, the inspector performed an in-office review of the overall pass/fail results of the individual operating examinations and the crew simulator operating examinations in accordance with Inspection Procedure (IP) 71111.11, "Licensed Operator Requalification Program." These results were compared to the thresholds established in Section 3.03, "Requalification Examination Results," of IP 71111.11.
The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam completed on December 9, 2021
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the Control Room during Unit 2 turbine stop valve testing at RTP on November 10, 2021.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator requalification exams which took place in the Unit 3 simulator on October 19, 2021 and October 20, 2021.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (4 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) HPCI functions 073-B, reactor pressure vessel (RPV) level makeup, and 073-C, circulating condensate in a closed loop for condensing steam on October 18, 2021
- (2) Emergent failure of 3B Fuel Pool Cooling and Cleanup (FPCC) Pump Motor due to all 3 phases grounded on November 12, 2021
- (3) Wide Range Gaseous Effluent Radiation Monitoring System (WRGERMS) function 90-B due to recorder input card failure on July 6, 2021
- (4) Automatic Load shed shedding and sequencing function 574-E, due to the Division I load shed relay BFN-0-RLY-231-A7 failing to actuate during a surveillance on September 23, 2021
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Elevated site aggregate risk (yellow) from various planned work activities including the 3B Electric Board Room Air Conditioning Unit maintenance window per work order (WO) 121004265 on November 18, 2021
- (2) Elevated site aggregate risk (yellow) from various planned work activities including inspection and removal of debris from CCW Pit 2A per WO 121544782 and the performance of Unit 2 Fuel inspections per WO 120657400 on November 17, 2021
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (7 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 2, Hand switch for Drywell floor drain outboard isolation valve does not spring return to Auto under condition report (CR) 1727699 on October 15, 2021
- (2) Unit 1, Increasing trend in the moisture content in oil samples from the HPCI turbine documented on October 25, 2021
- (3) Units 1 and 2, B Diesel generator (DG) left bank dryer 1 and 2 exhausted identified on October 21, 2021
- (4) Unit 1, Refueling Floor Exhaust and Reactor Building Exhaust Monitors failed low on November 16, 2021
- (5) Unit 2, 250VDC emergency high pressure makeup battery bank incomplete surveillance on November 30, 2021
- (6) Unit 1, 1B Unit Station Service Transformer Load Tap Changer Electronic Voltage Regulator on December 3, 2021
- (7) Unit 2, RHR heat exchanger outlet valve, 2-FCV-23-46, failure to fully close remotely from the main control room on December 9, 2021
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) BFN-21-043-01, Replace obsolete Unit 2 RPV High Pressure Tobar transmitter with Rosemount 3152N for 2-PT-003-0022BB on November 16, 2021
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
(1)3A DG following battery cell replacement on October 8, 2021 (2)2-PT-003-0022BB Unit 2 RPV high pressure transmitter replacement on November 18, 2021 (3)3A DG oil gallery fill check valve replacement on November 19, 2021
- (4) Unit 1 Turbine Stop Valve No. 4 Rod End Bearing Replacement and post maintenance test on December 9, 2021
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Unit 1 Power Suppression Testing to locate a potential fuel assembly defect in accordance with 0-TI-307, Power Suppression Testing was completed on December 12, 2021
FLEX Testing (IP Section 03.02) (2 Samples)
- (1) Flex 480Vac Portable Generators 2A and 2B full load performance tests performed under WO's 120704998 and 120704999, respectively on March 22, 2021
- (2) Flex Maintenance Preventive Maintenance (PM) 79379 completed on 2A 480VAC Turbine Marine Portable Generator, BFN-0-GEN-360-0002A per WO 121802447 on December 7, 2021
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) On December 8, 2021, inspectors observed and evaluated the operations training crew in response to an unexpected lowering of feedwater temperature from greater than 80 percent power and its effect on maintaining margin to the Maximum Extended Load Line Limit Analysis Plus (MELLLA+). As the scenario progressed, a leak in the drywell developed resulting in rising drywell pressure and a loss of all level 3 injection systems. Ultimately, the crew was forced to emergency depressurize and enter the appropriate emergency operating instructions and classify the event using the emergency plan implementing procedures.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 02.01)===
- (1) Unit 1 (October 1, 2020 - September 30, 2021)
- (2) Unit 2 (October 1, 2020 - September 30, 2021)
- (3) Unit 3 (October 1, 2020 - September 30, 2021)
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02) (3 Samples)
- (1) Unit 1 (October 1, 2020 - September 30, 2021)
- (2) Unit 2 (October 1, 2020 - September 30, 2021)
- (3) Unit 3 (October 1, 2020 - September 30, 2021)
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (3 Samples)
- (1) Unit 1 (October 1, 2020 - September 30, 2021)
- (2) Unit 2 (October 1, 2020 - September 30, 2021)
- (3) Unit 3 (October 1, 2020 - September 30, 2021)
71152 - Problem Identification and Resolution (PI&R)
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in missed or incomplete required tests or inspections that might be indicative of a more significant safety issue.
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Level 3 evaluation and corrective actions associated with human performance related to C2 residual heat removal service water pump failure on October 19, 2021.
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 50-259, 260, and 296/2020-02-00 and 01, Standby Gas Treatment (SGT)
System Train B Inoperable Longer Than Allowed by Technical Specifications (TS).
ADAMS Accession: MLs 20349A310 and 21043A098. The circumstances surrounding this LER are documented in the results section.
- (2) LER 50-260/2021-002-00 for Browns Ferry Nuclear Plant, Unit 2, Main Steam Relief Valves Lift Settings Outside of Technical Specification Required Setpoints. The circumstances surrounding this LER are documented in the results section.
INSPECTION RESULTS
Browns Ferry Nuclear Plant, Unit 2, Main Steam Relief Valves Lift Settings Outside of Technical Specification Required Setpoints Cornerstone Severity Cross-Cutting Aspect Report Section Not Applicable Severity Level IV NCV 05000260/2021004-01 Open/Closed
Not Applicable 71153 A self-revealed Severity Level IV NCV of Technical Specification (TS) 3.4.3 and TS 3.0.4 was identified when the licensee discovered, through as found test results, that five of thirteen Main Steam Relief Valves (MSRVs) that were removed for testing had as found lift settings outside of the +/-3 percent setpoint band required for their operability.
Description:
The Browns Ferry Unit 2 TS 3.4.3 requires twelve of the thirteen MSRVs to be operable while in Modes 1, 2, and 3. On June 3, 2021, the Tennessee Valley Authority was notified of as-found testing results that five MSRVs from Unit 2 were outside of the +/-3 percent setpoint band required for operability. It was determined that one of these MSRVs failed due to corrosion bonding between the pilot valve disc and seat. The other four were determined to have failed due to the relaxation of the setpoint spring over time. More than one MSRV was considered to be inoperable during the entire operating cycle from April 8, 2019, to February 27, 2021 and longer than permitted by TS 3.4.3. Additionally, TS 3.0.4 requires that when a limiting condition for operation (LCO) is not met, entry into an applicable Mode or specified condition is not permitted unless the associated actions permit continued operation. On four separate occasions, (October 7, 2019; May 22, 2020; June 10, 2020; and July 27, 2020), BFN Unit 2 entered a TS 3.4.3 Applicable Mode when LCO TS 3.4.3 Required Actions were not met. Therefore, Unit 2 was in violation of TS 3.0.4.
The affected valves remained capable of maintaining reactor pressure below the American Society of Mechanical Engineers code limit of 1375 psig. All thirteen of the MSRV pilot valves have been replaced during the Unit 2 Spring 2021 refueling outage. The previous corrective action from LER 05000260/2019-002-00 to apply a platinum coating to the pilot using the plasma enhanced magnetron sputtering deposition method (PEMS), which improves the quality and adhesion of the coating, had not yet been implemented.
Corrective Actions: The licensee replaced all thirteen MSRV pilot valves during the Spring 2021 refueling outage. The installed valves have implemented corrective actions from past occurrences of corrosion bonding that include preparing the pilot discs in accordance with the revised procedure and vendor recommendations. The currently installed refurbished valves had platinum coatings applied utilizing the PEMS deposition method, and as-left values were verified to be within +/- one percent of their setpoints.
Additionally, the licensee is revising procedure MCI-0-001-VLV002 to include stricter criteria for spring testing, so springs might be replaced prior to the point of significant relaxation resulting in as-found setpoint testing failures.
Corrective Action References:
CRs 962223, 1286467, 1410577, 1521190, 1658693, and 1699286
Performance Assessment:
The NRC determined this violation was not reasonably foreseeable and preventable by the licensee and therefore is not a performance deficiency.
Enforcement:
Severity: This violation is characterized as a Severity Level IV NCV based on its similarity to SLIV example 6.1.d.1 in the Enforcement Policy. The inspectors also reviewed NRC Enforcement Policy, Section 2.2.1, "Factors Affecting Assessment of Violations", which states, in part, that in determining the appropriate enforcement response to a violation, the NRC considers, whenever possible, risk information in assessing the safety or security significance of violations and assigning severity levels. The inspectors determined the issue to be of very low safety significance because the valves remained capable of performing their required safety function.
Violation: Browns Ferry Nuclear Plant, Unit 2 TS Subsection 3.4.3, 'Safety/Relief Valves (S/RVs),' Condition A, requires that with one or more required S/RVs inoperable, that the unit be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Mode 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Contrary to the above, four required S/RVs were inoperable from April 8, 2019, to February 27, 2021, and the unit did not enter Mode 3 and Mode 4 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, respectively.
Browns Ferry Nuclear Plant, Unit 2 TS Section 3.0, 'LCO Applicability', Subsection LCO 3.0.4, requires, in part, that when an LCO is not met, entry into a mode or other specified condition in the applicability shall only be made when the associated actions to be entered permit continued operation in the mode or other specified condition in the applicability for an unlimited period of time. Contrary to the above, on October 7, 2019; May 22, 2020; June 10, 2020; and July 27, 2020, BFN Unit 2 entered a TS 3.4.3 applicable mode when LCO TS 3.4.3 required actions were not met.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Licensee-Identified Non-Cited Violation 71153 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Browns Ferry Nuclear Plant, Unit 1, 2 and 3 TS Limiting Condition for Operation (LCO) 3.6.4.3, requires that three SGT subsystems shall be operable in Modes 1, 2, and 3, during operations with a potential for draining the reactor vessel. LCO 3.6.4.3 Condition A requires that, with one SGT subsystem inoperable, the subsystem must be restored to operable status within 7 days. Contrary to the above, the licensees past operability evaluation determined that SGT train B was inoperable from October 13, 2020 at 1200 (Central Daylight Time) CDT, to October 20, 2020 at 1330 CDT which exceeded TS allowed time because the breaker had a loose lead wire at the lug termination and would not have functioned properly during a seismic event. The apparent cause was a lack of guidance in the troubleshooting plan procedure when the breaker is required to be removed for inspection. Also, the licensee failed to develop an operational decision-making issue (ODMI),or adverse condition monitoring plan (ACMP) or other suitable monitoring plan for continued monitoring of the component following completion of the troubleshooting plan procedure when the root cause of the tripped breaker could not be determined per NPG-SPP-06.14, Section 3.4, Undetermined Root
Cause.
Significance/Severity: Green. The inspectors assessed the significance of the finding using Appendix A, Significance Determination Process for Findings At-Power. Using IMC 0609, Appendix A, Exhibit 3, the inspectors determined that this finding was of very low safety significance (Green) because the finding only represents a degradation of the radiological barrier function provided for the SGT system. The SGT Train A and C were available and operable during that period.
Corrective Action References: Condition Reports 1649674,1645805 and
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 26, 2022, the inspectors presented the integrated inspection results to Mr.
Daniel Komm and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR 1713635, 1738621
Procedures
0-TI-599
External Flood Protection
Rev 2
MPI-0-000-INS001
Inspection of Flood Protection Devices
Rev 19
MPI-0-260-DRS001
Inspection and Maintenance of Doors
Rev 56
Work Orders
21443882, 121558063,
21545209, 121498231,
21257208, WO 2332051
Corrective Action
Documents
CR 1725900
Drawings
0-47E865-4
Flow Diagram Ventilation and Air Conditioning Air Flow
Rev 67
0-47E866-3
Flow Diagram Heating and Air Conditioning Hot and
Chilled Water
Rev 37
1-47E610-71-1
Mechanical Control Diagram RCIC System
Rev 20
1-47E813-1
Flow Diagram Reactor Core Isolation Cooling System
Rev 42
3-47E811-1
Flow Diagram Residual Heat Removal System
Rev 73
3-47E811-1
Flow Diagram Residual Heat Removal System
Rev 73
Miscellaneous
Design Criteria
Document, BFN-50-7074
Residual Heat Removal System
Rev 30
Technical Specification Bases Section 3.7.4
Control Room Air Conditioning (AC) System
UFSAR Section 10.12
Heating, Ventilating and Air-Conditioning Systems
Procedures
0-OI-31
Control Bay and Off-Gas Treatment Building Air
Conditioning System
Rev 166
1-OI-71
Reactor Core Isolation Cooling System
Rev 28
1-OI-71/ATT-1
Reactor Core Isolation Cooling System Attachment 1
Valve Lineup Checklist
Rev 15
1-OI-71/ATT-2
Reactor Core Isolation Cooling System Attachment 2
Panel lineup Checklist
Rev 14
1-OI-71/ATT-3
Reactor Core Isolation Cooling System Attachment 3
Rev 13
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Electrical Lineup Checklist
1-OI-71/ATT-4
Reactor Core Isolation Cooling System Attachment 4
Instrument Inspection Checklist
Rev 12
3-OI-74
Residual Heat Removal System
Rev 132
3-OI-74/Attachment 1
Valve Lineup Checklist Unit 3
Rev 88
3-OI-74/Attachment 3
Electrical Lineup Checklist
Rev 94
Calculations
EDQ099920110010
NFPA - Nuclear Safety Capability Analysis
Rev 55
MDQ0009992012000101 BFN Units 1, 2, & 3 Detailed Fire Modeling Report
Rev 10
MDQ0009992012000104 BFN Scoping Fire Modeling Scenario Report
Rev 11
Fire Plans
FPR-Volume 2
Fire Protection Report Volume 2
Rev 68
Miscellaneous
NFPA 805 Fire
Protection Report
Appendix F
Fire Area 13
Rev 4
Procedures
NPG-SPP-09.17
Temporary Equipment Control
Rev 10
NPG-SPP-18.4.7
Control Transient Combustibles
Rev 15
NPP-SPP-01.3
Housekeeping
Rev 8
71111.11Q Miscellaneous
JPM Loss of Power to all
U3 4kv Shutdown
Boards >15min (SS1)
Loss of Power to all U3 4kv Shutdown Boards >15min
(SS1)
Rev 4
JPM Respond to a
Control Rod Drift In
Respond to a control rod drift in
Rev 3
LOR-EXAM-07
License Operator Requalification Exam 7
Rev 4
Procedures
2-TI-380
Power Ascension Turbine Valve Test
Rev 6
OPDP-1
Conduct of Operations
Rev 53
Work Orders
2373147
Corrective Action
Documents
CR 1114188, 1153334,
1160196, 1179483,
1183196, 1193943,
28065, 1263268,
1341458, 1429497,
1438077, 1609456,
1437895, 1532170,
1532094, 1532119,
1730569, 1705730,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1716247, 1653680,
22027, 1577241,
23229, 1732595
Engineering
Evaluations
CDE 2344
WRGERMS
Rev 1
CDE 2419
WRGERMS
Rev 2
CDE 2460
WRGERMS
Rev 1
CDE 2530
WRGERMS
Rev 4
CDE 2541
Automatic Load Shedding and Sequencing
Rev 3
CDE 2545
Automatic Load Shedding and Sequencing
Rev 1
Miscellaneous
Unit 1, 2 & 3 Function 073-B & C, HPCI (a)(1) Plan
Rev 7
(06/24/2020)
BFN-3-MTR-07B-0015
Equipment Failure Investigation Checklist
11/29/2021
Procedures
0-TI-346
Maintenance Rule Performance Indicator Monitoring,
Trending, and Reporting - 10CFR50.65
Rev 54
Work Orders
2484401, 122484839
Procedures
NPG-SPP-07.3
Work Activity Risk Management Process
Rev 36
Work Orders
WO 121544782 and
20657400
Corrective Action
Documents
CR 1727699, 1729940,
1730058,1730059,
1730062, 1730063,
1736195, 1736676,
1692216, 1710585,
1712295
Drawings
0-45E758-1
Wiring Diagram Supplemental Diesel Generator 4160V
Distribution Board Single Line
Rev 4
0-45E758-2
Supplemental Diesel Generator Start and Indication
Schematic Diagram
Rev 2
0-47E861-2
Flow and Control Diagram Diesel Starting Air System
and Diesel Generator B
Rev 13
0-47E861-2A
Flow Diagram Diesel Starting Air System Diesel Gen B
Rev 9
0-730E927-15
Primary Containment Isolation System
Rev 29
1-47E605-18
Mechanical Layout for Control Panel 9-25
Rev 1
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-45E722-3
Wiring Diagram 4kV EHPM Bd 2 Single Line Diagram
Rev 0
2-45E725-4
Wiring Diagram 250VDC and 208-102VAC EHPM Distr
Pnls Single Line Diagram
Rev 1
2-45E725-6
Wiring Diagram 250VDC Distr Pnl 2-BDDD-7-5
Connection Diagram
Rev 0
2-47E858-1
Flow Diagram RHR Service Water System
Rev 35
2-730E927-1A
PCIS System Elements Diagram
Rev 12
Miscellaneous
BFN-50-7077
Radwaste System Design Criteria
Rev 9
BFN-VTD-T147-0539
U-1 Terry Steam Turbine Co. Lubrication System
Rev 0
BFN-VTD-W305-0030
Worcester Controls Installation, Operation, and
Maintenance Instructions Series 39 Pneumatic Actuator
Rev 2
Oil Sample Data from
Unit 1 HPCI Turbine
Jan 2019 -
Oct 2021
UFSAR Table 5.2-2
Principle Primary Containment Penetrations and
Associated Isolation Valves
Rev 29
Operability
Evaluations
Functionality Evaluation Documentation for CR 1736676
CR 1737884
11/29/21
Procedures
0-GOI-300-1, Attachment
Unit 1 Reactor Building Operator Round Logs
Rev 272
0-OI-82
Standby Diesel Generator System
Rev 175
0-TI-230L
Lubrication Oil Analysis & Monitoring Program
Rev 15
2-ARP-9-3A
Alarm Response Procedure for Panel 9-3
Rev 57
EPI-0-007-BAT003
EHPM 250V DC Battery Bank Inspection and
Performance Test
Rev 1
OPDP-8
Operability Determination Process and Limiting
Conditions for Operation Tracking
Rev 28
Work Orders
Corrective Action
Documents
1735647
Engineering
Changes
BFN-21-043-01
Replace obsolete TOBAR pressure transmitter with
Rosemount 3152N for 2-PT-003-0022BB
Rev 0
Work Orders
2244994
Miscellaneous
Support refute matrix document for 3A DG unexpected
shutdown
11/03/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
1-SR-3.3.1.1.8(8)
Turbine Stop Valve Closure - RPS and RPT Trip
Channel Functional Test
Rev 26
2-SR-3.3.1.1.10(3B)
Reactor Pressure System High Reactor Pressure
Instrument Ch B1 Calibration
Rev 14
3-SR-3.8.6.2(DG 3A)
Quarterly Check of Diesel Generator 3A Battery
Rev 11
ECI-0-254-BAT001
Equalize Charging the Diesel Generator Battery Bank
Rev 15
ECI-0-254-BAT002
Replacement and Cleaning of the 125V DC Diesel
Generator Battery Cells
Rev 7
Work Orders
21621041, 122504080,
2508295, 122244994,
2412002, 121637765,
2451792
Work Instruction: Remove/Replace Defective Cell #38
Rev 0
Engineering
Changes
DCN 71470
Stage 480V Power Supply and Support Equipment to
Charge Unit Battery Charges
Rev B
Miscellaneous
1-SR-3.1.3.5(A)
Control Rod Movement and Control Rod Drive Problem
Data Sheets
2/09/2021 -
2/13/2021
CI-705
Fuel Performance and Isotopic Trends
Rev 49
Procedures
0-TI-307
Power Suppression Testing
Rev 15
0-TPP-ENG-632 (Bases)
Diverse and Flexible Coping Strategies (FLEX) Program
Bases Document
Rev 5
FMS-FLEX Generator-1
Fleet Maintenance Strategy FLEX-Generator-T3 NET
Diesel Driven
Rev 2
NPG-SPP-08.4
Fuel Reliability Program
Rev 1
PM Job Plan BFN-79376
25KW/480VAC CT Generator Maintenance (Quarterly)
Rev 0
Work Orders
20704998, 121802447
Procedures
OPL175S474
Operations and Reactor Engineer Combined Reactivity
Training
Rev 0
71151
Miscellaneous
BFN Unit 1 1E01 1E03
1E04 Data by Month
Performance Indicator Data for Unit 1 for 1E01, 1E03,
and 1E04
10/21/2021
BFN Unit 2 1E01 1E03
1E04 Data by Month
Performance Indicator Data for Unit 2 for 1E01, 1E03,
and 1E04
10/21/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
BFN Unit 3 1E01 1E03
1E04 Data by Month
Performance Indicator Data for Unit 3 for 1E01, 1E03,
and 1E04
10/21/2021
ESOMS logs for Units 1,
and 3
Operator Logs for units 1, 2, and 3 from 10/1/20 through
9/30/21
10/21/2021
Corrective Action
Documents
CR 1716888, 1717954
Miscellaneous
Functional Area Gap
Analysis for CR 1717954
Level of Effort
Classification Matrix for
CR 1716888
Performance Analysis
Worksheet for CR
1716888
Procedures
NPG-SPP-22.103
Performance Assessment and Monitoring
Rev 14
NPG-SPP-22.206
Verification Program
Rev 7
NPG-SPP-22.300
Corrective Action Program
Rev 22
Corrective Action
Documents
CRs 1649674, 1645805
and 1644285
Procedures
Electrical Corrective
Instruction, ECI-0-000-
BKR008
Testing and Troubleshooting of Molded Case Circuit
Breakers and Motor Starter Overload Relays
Revisions
018 and 019
General Operating
Instruction, 0-GOI-300-2
Electrical
Revision
0183
NPG-SPP-01.12
TVA Nuclear Event Response Process,
Revision
0018
NPG-SPP-06.14
Guidelines for Planning and Execution of
Troubleshooting Activities
Revision
0010
OPDP-11
Operational Decision-Making Issue Evaluation Process
Revision
0011
Work Orders
21663729, 119696878,
20897332, and
20897333