IR 05000324/2022002

Integrated Inspection Report 05000324/2022002 and 05000325/2022002

ML22216A254
Person / Time
Site:	Brunswick
Issue date:	08/05/2022
From:	Matthew Fannon NRC/RGN-II/DRP/RPB4
To:	Krakuszeski J Duke Energy Progress
References
IR 2022002
Download: ML22216A254 (16)

Text

SUBJECT:

BRUNSWICK STEAM ELECTRIC PLANT - INTEGRATED INSPECTION REPORT 05000324/2022002 AND 05000325/2022002

Dear Mr. Krakuszeski:

On June 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Brunswick Steam Electric Plant. On July 20, 2022, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.

No findings or violations of more than minor significance were identified during this inspection.

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, Matthew S. Fannon, Chief Reactor Projects Branch 4 Division of Reactor Projects Docket Nos. 05000324 and 05000325 License Nos. DPR-62 and DPR-71

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000324 and 05000325

License Numbers: DPR-62 and DPR-71

Report Numbers: 05000324/2022002 and 05000325/2022002

Licensee: Duke Energy Progress, LLC

Facility: Brunswick Steam Electric Plant

Location: Southport, NC

Inspection Dates: April 01, 2022 to June 30, 2022

Inspectors: C. Curran, Resident Inspector A. Rosebrook, Senior Reactor Analyst M. Schwieg, Senior Reactor Inspector J. Seat, Senior Project Engineer G. Smith, Senior Resident Inspector J. Steward, Senior Resident Inspector

Approved By: Matthew S. Fannon, Chief Reactor Projects Branch 4 Division of Reactor Projects

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Brunswick Steam Electric 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

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

PLANT STATUS

Unit 1 began the period shutdown for a refueling outage. On April 2, 2022, the reactor was taken critical and a plant startup was commenced. On April 4, the main generator output breaker was closed and a power ascension was commenced. On April 5, power was stabilized at 30 percent rated thermal power (RTP) in order to perform condenser dimple plug testing to locate leaking water-box tubes. Following completion of dimple plug testing, a power ascension was commenced and Unit 1 reached 100 percent (full) RTP on April 15 following two rod improvements. Unit 1 continued to operate at full RTP until April 19 when power was reduced to 96 percent RTP due to a failure of a cell in the variable frequency drive (VFD) associated with the 'B' recirculation pump motor. Following the bypass of the 1B2 cell in the 'B' VFD, Unit 1 was restored to full RTP on the same day and continued to operate there until May 19 when power was reduced to 80 percent RTP due to a loss of one of the four Unit 1 off-site power lines (Weatherspoon). Following repairs to the Weatherspoon line, Unit 1 was restored to full RTP on May 21 and continued to operate at or near full RTP for the remainder of the inspection period.

Unit 2 began the period at full RTP and operated there until May 7, when power was reduced to 70 percent RTP in order to insert a second suppression rod due to an existing fuel leak. Following insertion of a second suppression rod, Unit 2 was restored to full power on May 8 and continued to operate there until May 20 when power was reduced to 70 percent RTP for the purpose of performing a control rod sequence exchange as well as insert a third suppression rod. Following the sequence exchange and suppression rod insertion, Unit 2 was restored to full RTP on May 25 following one rod improvement. Unit 2 continued to operate at or near full RTP for the remainder 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, 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.

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)

(1) From April 12 through April 14, 2022, the inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal high temperatures for the following systems:

offsite AC power systems and onsite alternate AC systems, including the switchyard and transformers

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) 2C and 2E main control room (MCR) heating, ventilating, air conditioning (HVAC)units while the 1D MCR HVAC unit was out-of-service (OOS) for replacement on April 26, 2022

(2) Unit 2 high pressure coolant injection (HPCI) system while the Unit 2 reactor core isolation cooling system was OOS for planned maintenance on April 26, 2022

(3) Unit 2 nuclear service water and conventional service water (CSW) while Unit 2 'B' CSW pump was OOS for planned maintenance on May 11, 2022

(4) Unit 2 B residual heat removal (RHR) train while A train was OOS for planned maintenance on May 25, 2022

(5) emergency diesel generators (EDGs) -2, -3, and -4 while EDG-1 was OOS for a maintenance outage on June 22, 2022

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 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) Fire area RB2-01-D in the Unit 2 southeast RHR room on April 14, 2022

(2) Control building HVAC room on April 26, 2022

(3) 1A, 1B, 2A, 2B battery rooms in the 23 elevation of the control building on May 5, 2022

(4) Unit 1 reactor building -17 elevation on May 5, 2022

(5) Service water building 20 and 4 elevations on May 10, 2022

(6) Unit 1 reactor building 20 elevation on May 11, 2022

Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the onsite fire brigade training and performance during announced fire drills conducted on May 18, 2022, in the service building HVAC room and on May 24, 2022, in the insulator shop (yard area).

71111.06 - Flood Protection Measures

Inspection Activities - Internal Flooding (IP Section 03.01) (2 Samples)

The inspectors evaluated internal flooding mitigation protections in the:

(1) safety-related manholes (NS3, NS2, 5NW) on April 21, 2022

(2) emergency diesel generator building and 4-day fuel oil tank rooms on May 18, 2022

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 1 reactor startup on April 2, 2022.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)

(1) The inspectors observed and evaluated two operating crews during a simulator exam on April 21, 2022. The simulator exam was part of the licensed operator continuing training cycle 2. The scenario consisted of a recirculation loop flow transmitter failure, a reactor building closed cooling water heat exchanger leak, a loss of off-site power, and a small break loss of coolant accident.

(2) On May 19, 2022, the inspectors completed a review and evaluation of a written exam given in licensed operator continuing training cycle 1 conducted during the first quarter of 2022.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 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) relay failure (high contact resistance) that resulted in a spurious partial Group 6 and secondary containment isolation (NCR 2410783) on January 4, 2022

(2) EDG-1 maintenance outage conducted from June 20 through June 29, 2022

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (6 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) emergent failure of reactor building radiation monitor on April 14, 2022

(2) emergent steam leak in the Unit 2 main steam isolation valve (MSIV) pit discovered on May 8, 2022

(3) elevated risk due to 2B CSW pump strainer planned maintenance from May 9 through May 12, 2022

(4) emergent failure of 1C CSW pump strainer shear pin on May 11, 2022

(5) elevated risk due to Unit 1 A train RHR outage on May 25, 2022

(6) elevated risk due to EDG-1 maintenance outage on June 23, 2022

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) 2-B32-F031B actuator rating exceeded (NCR 2414157)

(2) RHR valve weight analysis discrepancy (NCR 2417296)

(3) deterioration of concrete wall in Unit 2 reactor building (NCR 2305749)

(4) reanalysis of HPCI pump time limit to rated speed and flow (NCR 2419332)

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) control building HVAC modification (Engineering Change 417875) completed on June 16, 2022

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)

The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:

(1) 0PT-09.2 HPCI operability test after replacement of the flow controller FIC-R600 in accordance with (IAW) work order (WO) 20304709

(2) 2B standby gas treatment system (SBGT) system following planned maintenance to replace drain piping IAW WO 20372477

(3) 1A SBGT system following planned maintenance to recoat drain line piping IAW WO

===20377862

(4) 2B CSW pump strainer planned maintenance and inspection IAW WO's 20399034 and 20412939

(5) 0PT-09.2, HPCI operability test following replacement of the Unit 2 HPCI EGR servo motor IAW WO 20525661

(6) G31-F001, reactor water cleanup (RWCU) inboard suction valve following valve replacement IAW WO 20377862

(7) G31-F004, RWCU outboard suction valve following valve replacement IAW WO 20377862

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01)===

(1) The inspectors evaluated Unit 1 refueling outage (B1R24) activities from March 5, 2022 to April 4, 2022, when the main generator was synched to the grid.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:

Surveillance Tests (other) (IP Section 03.01) (1 Sample)

(1) Loss of offsite power/loss of coolant accident (LOOP/LOCA) test on April 7, 2022

Inservice Testing (IP Section 03.01) (1 Sample)

(1) Unit 2 'B' RHR quarterly surveillance on June 4, 2022

RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)

(1) Unit 1 reactor coolant system (RCS) leakage IAW 0OI-02.3, "Drywell Leakage Control," on June 30, 2022

71114.06 - Drill Evaluation

Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

The inspectors evaluated:

(1) A simulator examination (training evolution) given to two separate operating crews on April 22, 2022. The simulator examination included a drill/exercise performance opportunity.

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===

(1) Unit 1 (April 1, 2021 through March 31, 2022)

(2) Unit 2 (April 1, 2021 through March 31, 2022)

MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)

(1) Unit 1 (April 1, 2021 through March 31, 2022)

(2) Unit 2 (April 1, 2021 through March 31, 2022)

MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)

(1) Unit 1 (April 1, 2021 through March 31, 2022)

(2) Unit 2 (April 1, 2021 through March 31, 2022)

===71152A - Annual Follow-up Problem Identification and Resolution

Annual Follow-up of Selected Issues (Section 03.03)===

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) NCR 2379462: Reactor recirculation pump seal premature failure

71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends in operations and maintenance that might be indicative of a more significant safety issue.

INSPECTION RESULTS

Observation: Reactor Recirculation Pump Seal Premature Failure 71152A The inspectors conducted a detailed review of NCR 2379462, Reactor Recirculation Pump Seal Premature Failure. The inspectors chose this sample because it dealt with the barrier integrity cornerstone involving the recirculation pump seals. On February 15, 2021, the second stage seal of the Unit 2 'B' recirculation pump was noted to be degrading. Based on the rate of degradation, the decision was made to replace the seal package during the upcoming March 2021 refueling outage. Following replacement of both the 'A' and 'B' seal packages during the refueling outage, operators noted a similar degrading second stage seal on the Unit 1 'B' recirculation pump on April 19, 2021. The decision was made to enter a maintenance outage on April 30 as the rate of seal degradation was excessive and the seal would not last until the next refueling outage in March 2022. The recirculation pump seals have an expected life of six years, yet the inspectors observed that the seals are degrading prior to reaching the end of their expected life cycle.

The licensee performed a detailed root cause analysis in order to understand the failure mechanism and develop corrective actions to address the deficiencies. The root cause was determined to be self-induced electro-corrosion of the second stage secondary seal.

Several corrective actions have been implemented including the replacement of all 4 seals on both units. The inspectors noted that this will be a long-term effort as the design changes to address the direct cause of the electro-corrosion are still being developed. The inspectors determined that the licensees plan to address this issue was reasonably commensurate with the safety significance of the equipment that might be affected by this type of equipment failure.

Observation: Semi-Annual Trend Review 71152S The inspectors performed a trend analysis on the licensees corrective action program to identify trends that could indicate the existence of a more significant safety issue. The inspectors focused their review on equipment performance trends, but also considered the results of inspector daily condition report screenings, licensee trending efforts, and licensee human performance results. The review nominally considered the 6-month period of January

- June 2022, although some examples extended beyond those dates when the scope of the trend warranted. The inspectors compared their results with the licensees analysis of trends.

Additionally, the inspectors reviewed the adequacy of corrective actions associated with a sample of the issues identified in the licensees trend reports. The inspectors also reviewed corrective action documents that were processed by the licensee to identify potential adverse trends in the condition of structures, systems, and/or components as evidenced by acceptance of long-standing non-conforming or degraded conditions.

During this review, the inspectors noted the reemergence of a negative trend with respect to reactor fuel performance. In Brunswick inspection report 05000324/2019002 and 05000325/2019002 (ADAMS Accession No. ML19221B744), the inspectors noted a negative trend based on three separate fuel cycles experiencing fuel failures. Following these failures, the licensee aggressively addressed the failures by performing detailed root cause evaluations. No definitive cause was noted. However, some of the failures were attributed to potential negative effects from foreign material. Additionally, one failure was attributed to a manufacturing defect. In order to address the foreign material, the license chose to clean all fuel assemblies during the upcoming refueling outages as well as perform a foreign object search and retrieval (FOSAR) activity. As of June 30, 2022, the fuel cleaning and FOSAR activities have been completed on both Unit 1 and Unit 2 during the most recent refueling outages. Since the initial determination of a negative trend in 2019, the inspectors noted two more cycles (Unit 1 in 2020 and Unit 2 in 2022) where fuel failures were encountered.

Despite the fuel cleaning and FOSAR efforts, Unit 2 recently experienced another fuel failure in April 2022 which necessitated flux suppression. Even given the flux suppression, the Unit 2 reactor coolant system activity has remained elevated. In summary, the condition reports (CRs) noted below document that five of the past seven fuel cycles on Unit 1 and Unit 2 experienced fuel leaks. Fuels leaks typically drive the licensee to suppress the neutron flux of the affected fuel assembly by inserting control rod(s) in the vicinity of the fuel leak. The inserted control rod can result in reduction of margin to thermal limits, limit rates of power increase, and increase the number of rod programming changes. The inspectors discussed this negative trend with the licensee.

• CR 2416401 (Unit 2, 2022)

• CR 2323829 (Unit 1, 2020)

• CR 2276790 (Unit 1, 2019)

• CR 2176522 (Unit 2, 2018)

• CR 2078244 (Unit 1, 2016)

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

On July 20, 2022, the inspectors presented the integrated inspection results to John A.

Krakuszeski and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Miscellaneous SD-50 230 KV Electric Distribution System 01/14/2020

Procedures CSD-EG-ALL-Nuclear Switchyard Operating Guidelines 08/30/2018

2000.2

71111.04 Miscellaneous SD-37 Control Building Heating, Ventilation, and Air-Conditioning 16

System

SD-39 Emergency Diesel Generators 22

Procedures 0OP-37 Control Building Ventilation System Operating Procedure 75

0OP-39 Diesel Generator Operating Procedure 198

2OP-17 Residual Heat Removal System Operating Procedure 185

2OP-19 High Pressure Coolant Injection System Operating 147

Procedure

2OP-43 Service Water System Operating Procedure 175

SD-17 Residual Heat Removal System 20

SD-19 High Pressure Coolant Injection (HPCI) System 25

SD-43 Service Water System 27

71111.05 Engineering 288259 Seismic Verification of Fire Protection Piping 05/18/2022

Changes

Fire Plans CSD-BNP-PFP-Control Building Pre-Fire Plans 5

0CB

CSD-BNP-PFP-Miscellaneous Buildings Pre-Fire Plans - Protected Area 1

0MBPA

CSD-BNP-PFP-Power Block Auxiliary Areas Pre-Fire Plans (SW, RW, AOG, 4

0PBAA TY, EY, PDC, DGS, MCP)

Miscellaneous 0FPP-031 Fire Brigade Staffing Roster and Equipment Requirements 34

18-F-OS-01 Insulator Shop Fire Drill Scenario Guide 05/18/2022

21-F-SB-01 Service Building Air HVAC Room Fire Drill Scenario Guide 05/18/2022

Procedures 0AOP-13.0 Operation During Hurricane, Flood Conditions, Tornado, or 73

Earthquake

0PFP-013 General Fire Plan 55

0PLP-01.2 Fire Protection System Operability, Action, and Surveillance 51

Requirements

AD-EG-ALL-1520 Transient Combustible Control 13

Inspection Type Designation Description or Title Revision or

Procedure Date

CSD-BNP-PFP-Reactor Building Prefire Plans 2

1RB

71111.06 Corrective Action 555550 Fire Protection Piping Seismic Support Documentation 05/17/2022

Documents AS 681677-05 Assignment Summary 07/29/2019

Corrective Action 20537521 Work Order 05/19/2022

Documents

Resulting from

Inspection

Engineering DBD-144 External and Internal Flooding Topical Design Basis 1

Evaluations Document

PS-FP-G008 Analysis to Seismically Qualify Select Fire Protection Pipe 0

Supports in the Diesel Generator Building

Miscellaneous BNP-12-0104 Long Range Plan 05/18/2022

UFSAR section Diesel Generator Building Internal Flooding Protection 27

3.4.2.2

Work Orders 20335906 02 BNP Man Hole Inspection AD-EG-ALL-1214 05/24/2021

20449286 02 (LR) FOUR YEAR MAN HOLE INSPECTION PER AD-EG- 02

BNP-1214

20449286 02 INSPECT MAN HOLE, DOCUMENT EGR-NGGC-0351 02

INSPECTION

20449286 02 BNP Man Hole Inspection AD-EG-BNP-1214 10/11/2021

71111.11Q Miscellaneous LORX-202 Simulator Guide - Recirculation Loop 'A' flow transmitter 10b

failure, RBCCW high radiation, LOOP, Small Break LOCA

Segment 22-1 LOCT examination 2022 Cycle 1 01/13/22

Version A

Segment 22-1 LOCT Examination 2022 Cycle 1 01/19/22

Version B

Procedures 0GP-02 Approach to Criticality and Pressurization of the Reactor128

71111.12 Procedures AD-EG-ALL-1210 Maintenance Rule Program 3

AD-WC-ALL-ON-LINE WORK MANAGMENT 20

200

AD-WC-ALL-WORK IMPLEMENTATION AND COMPLETION 15

250

71111.13 Corrective Action 2426363 Unit 2 MSIV Pit Steam Leak 05/09/2022

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents

Procedures 0AP-025 BNP Integrated Scheduling 60

AD-OP-ALL-0201 Protected Equipment 9

AD-WC-ALL-On-Line Work Management 20

200

AD-WC-ALL-Work Implementation and Completion 15

250

AD-WC-ALL-Work Activity Integrated Risk Management 13

0410

Work Orders 20225913 2-MS-F038D-MO, Backseat Valve Potential MSIV Pit Steam 05/10/2022

Leak

71111.15 Calculations 0HPCI-0011 HPCI RESPONSE TIME REQUIREMENT 002

Corrective Action Action Request: 2-B32-F031B Actuator Rating Exceeded 01/31/2022

Documents 02414157

Action Request: RHR Valve Weight Analysis Discrepancy 02/23/2022

2417296

Corrective Action 20226189 Work Request to drive repairs noted during inspection of the 05/12/2022

Documents Unit 1 South Core Spray Room EL -17'

Resulting from 2427216 1-RB1-BLG-EL-17-1 Cosmetic Defect on Unit 1 SCE 05/12/2022

Inspection Concrete Columns

Drawings 9527-F-02501 Unit 1 Reactor Building Plan Below Grade EL (-) 17' - 0" 29

General Arrangement

F-01230 Unit 2 Reactor Building Concrete Plan EL 20' - 0" - West 16

Engineering A/R 02423550 50.59 Screen to Extend HPCI Response Time Rev 00

Evaluations A/R 02423553 10 CFR 50.59 Evaluation to extend HPCI response time Rev 00

Operability 2305749 Repair Cosmetic Defect Void in Unit 2 Drywell Exterior Wall05/12/2022

Evaluations AD-OP-ALL-0105 OPERABILITY DETERMINATIONS 6

Procedures 0SPP-CEM500 Installation of Concrete and Grout 25

AD-OP-ALL-0105 Operability Determinations 6

71111.18 Engineering EC 417875 50.59 Screen for EC 417875 Rev 00

Changes EC 417875 CB HVAC Condensing Unit 1D Replacement Rev 015

Engineering A/R 2391929 50.59 Screen for EC 417875 Rev 00

Evaluations

Inspection Type Designation Description or Title Revision or

Procedure Date

Procedures PD-EG-ALL-1130 Engineering Change Program Rev 1

71111.19 Corrective Action 2426126 1-E41-V6 Flow Inst Connection Spraying Leak 05/05/2022

Documents

Resulting from

Inspection

Procedures 0PLP-20 Post-Maintenance Testing Program 55

0PM-STR500

R.P. Adams Self-Cleaning Strainers, Model VWS 10 through 37

0PT-09.2 HPCI System Operability Test 153

Work Orders 20304709 1-E41-FIC-R600, Replace Controller, HPCI Turb Flo Ind 05/03/2022

Controller

20372477 2B SBGT Drain Line Repairs 05/16/2022

20377862 Recoat 1A SBGT Drain Line Piping 05/20/2022

20399034, 2B CSW Strainer maintenance 05/20/2022

20412939

20525661-06 Unit 2 HPCI Servo Replacement 3/12/22

71111.20 Procedures 0GP-02 Approach to Criticality and Pressurization of the Reactor128

0GP-03 Unit Startup and Synchronization 98

0GP-04 Increasing Turbine Load to Rated Power 132

71111.22 Procedures 0OI-02.3 Drywell Leakage Control 9

0PT-08.2.2B LPCI/RHR SYSTEM OPERABILTIY TEST - LOOP B 110

0PT-12.1A No.1 Emergency Diesel Generator LOOP/LOCA Loading 11

Test

71114.06 Procedures AD-EP-ALL-002 NRC Regulatory Assessment Performance Indicator 7

Guideline Emergency Preparedness Cornerstone

AD-EP-ALL-0101 Emergency Classification 3

CSD-EP-BNP-EAL Wallchart (Both Hot and Cold) 4

0101-02

71151 Engineering BNP-MECH-BNP Mitigating System Performance Index Plant Basis 2

Evaluations MSPI Document

BNP-PSA-069 NRC Mitigating System Performance Index (MSPI) PRA 17

Input Document

71152A Procedures AD-PI-ALL-0100 Corrective Action Program 27

71152S Procedures AD-PI-ALL-0100 Corrective Action Program 27

14