IR 05000456/2019002

Reissue - Braidwood Station, Units 1 and 2 - Integrated Inspection Report 05000456/2019002 and 05000457/2019002

ML19266A637
Person / Time
Site:	Braidwood
Issue date:	09/20/2019
From:	Karla Stoedter NRC/RGN-III
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
Shared Package
ML19266A656	List: IR 05000456/2019002
References
IR 2019002
Download: ML19266A637 (19)

Text

ber 20, 2019

SUBJECT:

REISSUEBRAIDWOOD STATION, UNITS 1 AND 2INTEGRATED INSPECTION REPORT 05000456/2019002 AND 05000457/2019002

Dear Mr. Hanson:

The U.S. Nuclear Regulatory Commission (NRC) identified the need to reissue NRC Inspection Report 05000456/2019002 and 05000457/2019002 dated July 26, 2019 (ADAMS Accession Number ML19210E060). Specifically, the basis for closing the unresolved item regarding the qualification of Limit Switch 2RY456 following the removal of a conduit seal required clarification to better describe the NRCs basis for closing the item. This unresolved item appears in the Inspection Findings section of this report. As a result, the NRC has reissued the report in its entirety with that section revised to correct the error.

On June 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Braidwood Station, Units 1 and 2. On July 2, 2019, the NRC inspectors discussed the results of this inspection with Ms. M. Marchionda, Site Vice President, and other members of your staff.

The results of this inspection are documented in the enclosed report.

The NRC inspectors did not identify any finding or violation of more than minor significance.

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.

Sincerely,

/RA/

Karla Stoedter, Chief Engineering Branch 2 Division of Reactor Safety Docket Nos. 05000456 and 05000457 License Nos. NPF-72 and NPF-77

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000456 and 05000457 License Numbers: NPF-72 and NPF-77 Report Numbers: 05000456/2019002 and 05000457/2019002 Enterprise Identifier: I-2019-002-0059 Licensee: Exelon Generation Company, LLC Facility: Braidwood Station, Units 1 and 2 Location: Braceville, Illinois Inspection Dates: April 01, 2019 to June 30, 2019 Inspectors: D. Kimble, Senior Resident Inspector J. Robbins, Reactor Inspector P. Smagacz, Resident Inspector Approved By: Karla Stoedter, Chief Engineering Branch 2 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Braidwood Station, Units 1 and 2 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 Type Issue Number Title Report Section Status URI 05000456,05000457/2 Qualification of Conduit Seal 71111.21N Closed 018012-01 Removal for 2RY456 Limit Switch

PLANT STATUS

Unit 1 began the inspection period operating at full power. With the exception of minor reductions in power to support scheduled testing activities or small load changes requested by the transmission system dispatcher, the unit remained operating at or near full power for the entire inspection period.

Unit 2 began the inspection period operating at full power. With the exception of minor reductions in power to support scheduled testing activities or small load changes requested by the transmission system dispatcher, the unit remained operating at or near full power for the entire 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 plant status activities described in IMC 2515 Appendix D, Plant Status and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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 Summer Readiness Sample (IP Section 03.01)

(1) The inspectors evaluated summer readiness of offsite and alternate alternating current (AC) power systems during the week ending June 22, 2019

71111.04 - Equipment Alignment Partial Walkdown Sample (IP Section 03.01)

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

(1) 1B Emergency Diesel Generator (EDG) with 1A EDG out of service for maintenance during the week ending April 6, 2019

(2) 1A Containment Spray (CS) with 1B CS out of service for planned maintenance during the week ending June 22, 2019

71111.05Q - Fire Protection Quarterly Inspection (IP Section 03.01)

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Fuel Handling Building, Fire Zone 12.1-0 during the week ending April 6, 2019

(2) 2A Residual Heat Removal (RH) Pump Room, Fire Zone 11.2A-2 during the week ending April 27, 2019

(3) Unit 1 Containment Pipe Penetration Area, Fire Zone 11.3-1 during the week ending April 27, 2019

(4) 2A EDG Room, Fire Zone 18.2-2 during the week ending June 22, 2019

71111.06 - Flood Protection Measures Inspection Activities - Internal Flooding (IP Section 02.02a.)

The inspectors evaluated internal flooding mitigation vulnerability and protection for the following plant area:

(1) Unit 2 'B' Essential Service Water (SX) Pump Room, Auxiliary Building Elevation 330' during the weeks ending May 18 through June 1, 2019

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) The inspectors conducted an evaluation of licensed operator performance in the Control Room during various observations of on-watch Operations shift crews during the weeks ending April 27 through June 29, 2019 Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated a graded simulator scenario for a crew of licensed operators on June 25, 2019

71111.12 - Maintenance Effectiveness Quality Control (IP Section 02.02)

The inspectors evaluated the licensee's maintenance and quality control activities associated with the following equipment performance issue:

(1) The failure of control power fuses for the 2A EDG as documented in Issue Report (IR)

4252176 during the weeks ending June 8 through June 29, 2019 Routine Maintenance Effectiveness Inspection (IP Section 02.01)

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) A 1B Auxiliary Feedwater (AF) Pump performance issue associated with diesel fuel oil seepage into the crankcase oil system as documented in IR 4238259 during the weeks ending April 20 through June 29, 2019

(2) An issue with the cubicle cooler fan motor bearing service life and run times for the chemical and volume control pump cubicle coolers as documented in IRs 4244994,

===4244974, and 4244975 during the weeks ending May 4 through June 29, 2019

71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01)

The inspectors evaluated the licensee's assessment of risk associated with the following planned and emergent work activities:

(1) Planned 2-year maintenance on the 1A EDG as document in Work Order (WO)4692594 during the week ending April 6, 2019

(2) Emergent maintenance on the 1B AF Pump as documented in WO 4908688 during the week ending April 13, 2019

(3) Starting battery capacity maintenance and testing for the 2B AF Pump as documented in WO 1836579 during the weeks ending April 20 through April 27, 2019

(4) Unit 1 System Auxiliary Transformer (SAT) 142-1 maintenance inspections as documented in WO 1945815 during the week ending May 11, 2019

(5) Ground isolation activities on direct current (DC) Bus 111 as documented in WO 4920701 during the weeks ending May 18 through June 29, 2019

(6) Emergent maintenance activities surrounding the failure of DC control power fuses for the 2A EDG as documented in IR 4252176 during the week ending June 1, 2019

71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 02.02)

The inspectors performed evaluations of the following issues with respect to equipment operability and/or functionality:

(1) The licensee's decision to isolate primary water to the 1C Reactor Coolant Pump (RCP) seal package standpipe as documented in IR 4224618 during the weeks ending April 20 through April 27, 2019

(2) Evaluation of excessive run time hours for the bearings on the 1B CV Cubicle Cooler fan motor as documented in IR 4244994 during the weeks ending May 4 through June 29, 2019

(3) Evaluation of the minimum bus voltages for the Unit 1 SAT outage window as documented in IR 4247579 during the week ending May 11, 2019

(4) Evaluation of intermittent grounds on DC Bus 111 as documented in IR 4248185 during the weeks ending May 18, 2019 through June 29, 2019

(5) Evaluation of degraded conditions for the valve 2AF005G manual loader (2HK-AF036B) as documented in IR 4249077 during the week ending May 18, 2019

(6) Evaluation of degraded performance associated with valve 2SX124A as documented in IR 4253330 during the weeks ending June 8 through June 15, 2019

71111.19 - Post-Maintenance Testing Post Maintenance Test Sample (IP Section 03.01)

The inspectors evaluated the adequacy of the following post maintenance testing activities:

(1) Functional and operational testing for 1B SX Pump following planned oil cooler maintenance during the weeks ending May 18 through May 25, 2019

(2) Functional and operational testing for check valve 2CC070B following disassembly and inspection as documented in WO 1939834 during the weeks ending May 18 through May 25, 2019

(3) Functional testing following investigation and repair of a high temperature connection associated with 1AP27E, Division 1, during the week ending May 25, 2019

(4) Functional testing following repairs on the cubicle cooler flow indicator sensing line for the 1B CS pump during the week ending June 22, 2019 71111.21N - Design Bases Assurance Inspection (Programs)

The inspectors conducted the following activities:

Select Sample Components to Review - Risk Significant/Low Design (Inside/Outside Containment) (IP Section 02.01) (1 Partial)

(1) (Partial)

The inspectors reviewed actions to close Unresolved Item 05000456,05000457/2018012-01; "Qualification of Conduit Seal Removal for 2RY456 Limit Switch." These reviews by the inspectors did not constitute a separate stand-alone inspection sample. Rather, they were an integral part of the original inspection sample for this previously documented item.

==71111.22 - Surveillance Testing The inspectors evaluated the performance and conduct of the following surveillance testing activities:

Surveillance Tests (other) (IP Section 03.01)==

(1) 2BwOSR 3.8.1.2-1: 2A Diesel Generator Semiannual Operability Surveillance - Timed Fast Start during the week ending April 13, 2019

(2) 1BwOS MS-Q1: Unit 1 Main Condenser Steam Dump Operability Surveillance -

Timed Fast Opening during the week ending April 13, 2019

(3) 2BwOSR5.5.8.SI-10B: Group A Inservice Test (IST) Requirements for 2B Safety Injection Pump during the week ending June 22,

OTHER ACTIVITIES - BASELINE

71151 - Performance Indicator Verification The inspectors conducted a verification of the performance indicators listed below through a sample of the licensee's submitted data:

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

(1) Unit 1 (April 1, 2018, through March 31, 2019)

(2) Unit 2 (April 1, 2018, through March 31, 2019)

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

(1) Unit 1 (April 1, 2018, through March 31, 2019)

(2) Unit 2 (April 1, 2018, through March 31, 2019)

MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)

(1) Unit 1 (April 1, 2018, through March 31, 2019)

(2) Unit 2 (April 1, 2018, through March 31, 2019)

71152 - Problem Identification and Resolution Semiannual Trend Review (IP Section 02.02)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends involving multiple issues with the loose parts monitoring systems on both units that might be indicative of a more significant safety issue during the weeks ending May 3, 2019, through June 29,

INSPECTION RESULTS

Observation: Loose Parts Monitoring System Reliability 71152 The inspectors performed a review of plant issues, particularly those entered into the licensees CAP, associated with issues and failures of the loose parts monitoring systems on both units. The loose parts monitoring system is described in Section 4.4.6.4 of the stations Updated Final Safety Analysis Report (UFSAR) as a system that detects and alarms upon sensing unusual noises that might indicate a metallic loose part within the reactor coolant system. Operability requirements for the system in operational Modes 1 and 2 are set forth in Section 3.3.d of the stations Technical Requirements Manual (TRM).

During their review, the inspectors noted that there have been several loose parts monitoring system failures during the current operating cycles on both units. Currently, each unit has three (of a total of twelve available) loose parts monitoring system channels in a degraded and unavailable status, and due to accessibility issues with the equipment locations in containment each degraded channel will remain unavailable for the remainder of the units operating cycle. Given the systems overall significance, as indicated by its UFSAR and TRM descriptions and requirements, additional review of system maintenance practices may be warranted.

Additionally, during the course of the most recent inspection period, the inspectors noted that a spurious Unit 1 loose parts monitoring system alarm was frequently being received at the same time each morning on most days of the week over a several week period. Following discussions with licensee management regarding the vulnerabilities associated with spurious alarms causing the operating crews to become desensitized, this particular loose parts monitoring system problem was traced to a computer coding issue within the systems software and eliminated.

Unresolved Item Qualification of Conduit Seal Removal for 2RY456 Limit 71111.21N (Closed) Switch 05000456,05000457/2018012-01

Description:

The inspectors identified an unresolved item concerning the removal of the conduit seal from a NAMCO EA180 limit switch for 2RY456 Pressurizer Power Operated Relief Valve (PORV). Position indication of PORVs is a requirement outlined in NUREG-0737, Clarification of TMI Action Plan Requirements, Enclosure 1, Post-TMI Requirements for Operating Reactors, Item II.D.3, Valve Position Indication. These requirements were incorporated prior to license issuance and are part of Braidwoods current licensing basis.

The NAMCO EA 180 switch in question is located in containment and could be exposed to a high temperature steam environment during an accident. These switches were originally qualified for this environment by Westinghouse. As documented in the Regulatory Guide 1.89 discussion in Braidwood UFSAR, Appendix A, (Page A1.89-1): For Westinghouse Nuclear Steam System Supplier Class lE equipment, Westinghouse has met the requirements of IEEE Std 323-1974, "IEEE Standard for Qualifying Class lE Equipment for Nuclear Power Generating Stations" including the Nuclear Power Engineering Committee (NPEC) Position Statement of July 24, 1975, and Regulatory Guide 1.89, Revision 0, by providing an appropriate combination of the following: type testing, operating experience, qualification by analysis, and on-going qualification. This commitment has been satisfied by NRC review and approval of Westinghouse Topical Report WCAP-8587.

Subsequently, the licensee performed an analysis supporting removal of seals without affecting the environmental qualification.

Initially, the inspectors identified differences in the licensees analysis and the IEEE Std 323-1974 guidance and viewed this as a potential performance deficiency. After discussions with NRR technical staff and legal staff, the inspectors determined that no performance deficiency existed based on the following information:

In November 1974, Regulatory Guide 1.89, Qualification of Class IE Equipment for Nuclear Power Plants, was issued. Within this document it states:

The procedures described in IEEE Std 323-1974, "IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations,"' dated February 28, 1974, for qualifying Class IE equipment for service in light-water-cooled and gas-cooled nuclear power plants are generally acceptable and provide an adequate basis for complying with design verification requirements of Criterion III of Appendix B to 10 CFR Part 50 to verify adequacy of design under the most adverse design conditions subject to the following:

This regulatory guide was revised in 1984, following issuance of 10 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants. The revised guide contains a similar statement:

The procedures described by IEEE Std 323-1974, "IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations,"' are acceptable to the NRC staff for satisfying the Commission's regulations pertaining to the qualification of electric equipment for service in nuclear power plants to ensure that the equipment can perform its safety functions subject to the following:

Currently, Regulatory Guide 1.89 remains available for use and the view that IEEE Std 323-1974 represents an acceptable method for satisfying the Commission's regulations pertaining to the qualification of electric equipment for service in nuclear power plants remains unchanged.

The guidance found in IEEE Std 323-1974 is detailed and prescriptive. One issue that arose during inspection was not if IEEE Std 323-1974 represented an acceptable approach, but rather is it possible to meet requirements set forth in 50.49 and deviate from the guidance contained in IEEE Std 323-1974. With respect to meeting regulatory requirements, while IEEE Std 323-1974 has been endorsed by the NRC with clarification, 50.49 does not invoke any standard directly; i.e. a deviation from the guidance found in IEEE Std 323-1974 does not necessarily mean that a component is non-compliant with 10 CFR 50.49.

The requirements associated with environmental qualification can be found in 10 CFR 50.49. Multiple methods for qualification are identified in 10 CFR 50.49(f) including:

(f) Each item of electric equipment important to safety must be qualified by one of the following methods:

(1) Testing an identical item of equipment under identical conditions or under similar conditions with a supporting analysis to show that the equipment to be qualified is acceptable.

(2) Testing a similar item of equipment with a supporting analysis to show that the equipment to be qualified is acceptable.

(3) Experience with identical or similar equipment under similar conditions with a supporting analysis to show that the equipment to be qualified is acceptable.

(4) Analysis in combination with partial type test data that supports the analytical assumptions and conclusions.

The inspectors concluded that the information provided by the licensee was sufficient to address the inspectors concerns with both 10 CFR 50.49 and 10 CFR 50.59.

Corrective Action Reference(s): AR 4120790 - NRC Question on Environment Qualification Binder Evaluation of Limit Switches

EXIT MEETINGS AND DEBRIEFS

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

• On July 2, 2019, the inspectors presented the integrated inspection results to Ms. M. Marchionda, Site Vice President, and other members of the licensee staff.

• On July 10, 2019, the inspectors presented the closure of Unresolved Item 2018012-01 to Mr. S. MacArtney, General Design Engineering Manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Procedures 0BwOA ENV-1 Adverse Weather Conditions Unit 0 124

OP-AA-102-102 General Area Checks and Operator Field Rounds 16

OP-AA-108-107- Station Response to Grid Capacity Conditions 7

1001

OP-AA-108-111- Sever Weather and Natural Disaster Guidelines 18

1001

OP-BR-102-102- Augmented Operator Field Rounds 3

1001

WC-AA-107 Seasonal Readiness 21

71111.04 BwOP CS-E1 Electrical Lineup - Unit 1 Containment Spray System 4

Electrical Lineup

BwOP CS-M1 Operating Mechanical Lineup Unit 1 12

BwOP DG-E2 Electrical Lineup - Unit 1, 1B Diesel Generator 6

BwOP DG-M2 Operating Mechanical Lineup Unit 1, 1B Diesel Generator 17

71111.05A Fire Plans No. 104; Fire Auxiliary Building 364' Elevation RHR Pump 2A Room 1

Zone 11.2A-2

No. 114; Fire Auxiliary Building 364' Elevation Unit 1 Containment Pipe 1

Zone 11.3-1 Penetration Area

71111.05Q No. 104; Fire Auxiliary Building 364' Elevation Residual Heat Removal 1

Zone 11.2A-2 Pump 2A Room

No. 114; Fire Auxiliary Building 364' Elevation Unit 1 Containment Pipe 1

Zone 11/3-1 Penetration Area

No. 178; Fire Fuel Handling Building 401' Elevation 1

Zone 12.1-0

No. 179; Fire Fuel Handling Building 426' Elevation 1

Zone 12.1-0

No. 200; Fire Auxiliary Building 401' Elevation Diesel Generator 2A & 0

Zone 18.2-2 Switchgear Room Air Shaft

Procedures BwAP 1110-1 Fire Protection Program System Requirements 42

BwAP 1110-3 Plant Barrier Impairment Program 38

BwOP PBI-1 Plant Barrier Control Program 12

CC-AA-201 Plant Barrier Control Program 12

Inspection Type Designation Description or Title Revision or

Procedure Date

ER-AA-600-1069 High Risk Fire Area Identification 4

ER-BR-600-1069 Site List of High Risk Fire Areas - Braidwood Unit 1 and 0

Unit 2

OP-AA-201-004 Fire Prevention for Hot Work 16

OP-AA-201-007 Fire Protection System Impairment Control 0

OP-AA-201-009 Control of Transient Combustible Material 23

71111.06 0BwOA PRI-8 Auxiliary Building Flooding Unit 0 9

BwAP 1110-3 Plant Barrier Impairment Program 38

BwOP PBI-1 Plant Barrier Impairment Program Pre-Evaluated Barrier 3

Matrix

CC-AA-201 Plant Barrier Control Program 12

71111.11Q ER-AA-600 Risk Management 7

OP-11-101-113- 4.0 Crew Critique Guidelines 10

1006

OP-AA-101-111- Operations Standards and Expectations 22

1001

OP-AA-101-113 Operator Fundamentals 13

OP-AA-103-102 Watch Standing Practices 18

OP-AA-103-102- Strategies for Successful Transient Mitigation 2

1001

OP-AA-103-103 Operation of Plant Equipment 1

OP-AA-104-101 Communications 4

OP-AA-108-107- Interface Procedure Between BGE/COMED/PECO and 12

1002 Exelon Generation (Nuclear/Power) for Transmission

Operations

OP-AA-111-101 Operating Narrative Logs and Records 15

OP-AA-300 Reactivity Management 13

TQ-AA-10 Systematic Approach to Training Process Description 5

TQ-AA-150 Operator Training Programs 18

TQ-AA-155 Conduct of Simulator Training and Evaluation 9

TQ-AA-201 Examination Security and Administration 17

TQ-AA-306 Simulator Management 9

TQ-BR-201-0113 Braidwood Training Department Simulator Examination 22

Inspection Type Designation Description or Title Revision or

Procedure Date

Security Actions

71111.12 Corrective Action 0881124 Long Range Planning for 1VA06CD Motor Refurbishment 02/16/2009

Documents 4238259 1AF01PB Crankcase Oil Analysis Degrading Trend 04/10/2019

244974 1VA06SA Vibration Reading Results 04/30/2019

244975 2VA06SA Vibration Reading Results 04/302019

244994 1VA06CD Exceeds Run Time Threshold for Motor Bearings 04/30/2019

Procedures ER-AA-310-1002 Maintenance Rule Functions - Safety Significant 3

Classification

ER-AA-320 Maintenance Rule Implementation per NEI 18-10 0

ER-AA-320-1001 Maintenance Rule 18-10 - Scoping 0

ER-AA-320-1004 Maintenance Rule 18-10 - Performance Monitoring and 1

Dispositioning Between (a)(1) and (a)(2)

71111.13 Calculations BRW-97-0340-E Battery Duty Cycle and Sizing for the Braidwood Diesel 3

Driven Auxiliary Feedwater Pumps

Corrective Action 2667064 Lessons Learned - Unit 1 System Auxiliary Transformer 05/09/2016

Documents (SAT) Outage Temporary State Estimator Alarm Setpoint

235979 Coating Repairs Needed for the 1DG01KA-X2 Lower 04/03/2019

Stationary Head

235981 Coating Repairs Needed for the 1DG01KA-X2 Lower Pact 04/03/2019

End Channel Head

235983 Coating Repairs Needed for the 1DG01KA-X1 Upper Pact 04/03/2019

End Channel Head

235987 Debris Found Inside Stationary Head and Tubesheet 04/03/2019

1DG01KA-X2

235988 Degradation Found During Inspection of 1DG01KA-X1 04/03/2019

Upper Stationary Head

236145 Significant Amount of Oil in Air Sensing Line 04/04/2019

236908 1A Diesel Generator South Fuel Rack Positioner Cable 04/06/2019

Broke

236938 1A Diesel Generator Butterfly Valve Sticking 04/06/2019

238259 1AF01PB Crankcase Oil Analysis Degrading Trend 04/10/2019

240057 Battery Charger Lugs are Distorted on 2AF01EB-A Battery 04/16/2019

247173 ACB 1441 Would Not Close Following SAT Restoration 05/02/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

247555 Ground Connections Corroded 05/08/2019

247567 Unit 1 SAT LCO 4.0 Critique 05/08/2019

247579 Braidwood SAT Outage Restoration Delays 05/08/2019

248106 SAT 142-1 Received Unsatisfactory Doble Test on X3 05/10/2019

Bushing

248185 Direct Current Bus 111 Ground 05/11/2019

Engineering 620474 Evaluation of Single SAT Operation on Unit 1 for 2019 0

Evaluations

Procedures 1BwOSR 3.8.1.1 Unit 1 Offsite AC Power Availability Surveillance 5

2BwHS 384-6 24 Volt ESF Auxiliary Feed Diesel Battery BT2 and BT2 0

Performance Test

2BwHSR 3.7.5- 2B Diesel Auxiliary Feed Pump Battery Bank B Battery A 3

BA (2AF01EB-A) Capacity Test

2BwOS DC-Q4 24V DC Auxiliary Feed Pump 2B Battery Bank A and B 6

Quarterly Surveillance

BwHP 4006-023 Bus Disconnect Link Relocation on 6900 V SAT Buses 8

BwHP 4006-059 Operation of the Biddle/AVO Ground Fault Tracer 3

BwHP 4006-066 DC Bus Ground Location Using the Multi-Amp Battery 1

Ground-Fault Locator

BwHP 4006-074 Bus Disconnect Link Relocation on 4160 V SAT Buses 4

BwHS 4002-084 System Auxiliary Transformer Preventative Maintenance 15

Inspection

BwMP 3100-022 Diesel Generator 2 Year Inspection 38

BwMP 3200-014 Auxiliary Feedwater Pump Diesel Drive Unit Inspection and 22

Maintenance

BwOP AP-15 Isolating System Auxiliary Transformer (SAT) 142-1 with Unit 27

Unit Auxiliary Transformer (UAT) Energized

BwOP AP-20 Restoring System Auxiliary Transformer (SAT 142-2) with 21

Unit 1 UAT Energized

BwOP AP-54 With SAT 142-1 Isolated, Isolate SAT 142-2 and Restore 11

SAT 142-1 with Unit 1 UAT Energized

BwOP DC-E2 Electrical Lineup - Unit 1 Operating - 125 Vdc Division 11 9

ER-AA-330-009 ASME Section XI Repair/Replacement Program 16

ER-AA-335-015- VT-2 Visual Examination in Accordance with ASME 2013 0

Inspection Type Designation Description or Title Revision or

Procedure Date

2013

ER-AA-600-1042 On-Line Risk Management 11

MA-AA-716-230- Lubricant Sampling Guideline 5

1004

MA-BR-EM-4- Diesel Generator Electrical Inspection 16

09070

OP-AA-108-117 Protected Equipment Program 5

WC-AA-101-1006 On-Line Risk Management and Assessment 2

WC-AA-104 Integrated Risk Management 25

Work Orders 1836579 24 Volt Auxiliary Feed Battery Bank Capacity Test 04/15/2019

(2AF01EB)

1945815 1AP02E: Preventative Maintenance Inspection of SAT 142-1 05/07/2019

4692594 1DG01KA: 24 Month Inspection of the Diesel Generator 04/01/2019

4693700 1DG01EA: Diesel Generator Exciter Inspection (1A EDG) 04/01/2019

4908688 1AF01PB Crank Case Oil and Filter Change 04/12/2019

20701 DC Bus 111 Ground 05/13/2019

71111.15 Corrective Action 2667064 Lessons Learned - Unit 1 SAT Outage Temporary State 09/09/2016

Documents Estimator Alarm Setpoint

4194175 1PL01J Alarms Generate DC Bus 111 Ground Alarm 11/12/2018

209879 DC Bus 111 Ground Coming in with 1PL01J Panel Check 01/10/2019

23051 1RF008 Flowrate Trend Anomaly 02/24/2019

24618 1CV179 Cycling Excessively 02/28/2019

28652 1RF009 Elevated Reading 03/12/2019

29675 Unit 1 Floor Drain Sump Channel A Failed - PC002 03/15/2019

244974 1VA06SA Vibration Reading Results 04/30/2019

244975 2VA06SA Vibration Reading Results 04/30/2019

244994 1VA06CD Exceeds Run Time Threshold for Motor Bearings 04/30/2019

247579 Braidwood SAT Outage Restoration Delays 05/08/2019

248185 DC Bus 111 Ground 05/22/2019

249077 2HK-AF036B: Manual Loader for 2AF005G Failed - WO 05/15/2019

1893938

253330 2SX124A is Very Difficult to Operate 05/31/2019

254702 Erratic 2A CV Pump Cubicle Cooler SX Flow Rate 06/05/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

Engineering EC 628126 Performance of Cubicle Coolers 1VA06SA and 2VA06SA 0

Changes with One or Two Fans in Operation

Procedures 1BwOS DC-1a AAR-125 Vdc ESF Bus Ground 8

BwOL 3.8.4 DC Sources - Operating Technical Specification LCO 3.8.4 8

LCOAR

BwOP DC-23-111 125 Vdc Bus 111/113 Ground Detection 4

ER-AA-321 Administrative Requirements for Inservice Testing 13

ER-AA-600-1012 Risk Management Documentation 14

ER-AA-600-1045 Risk Assessments of Missed or Deficient Surveillances 7

OP-AA-106-101- Operational Decision Making Process 21

1006

OP-AA-108-111 Adverse Condition Monitoring and Contingency Planning 13

OP-AA-108-115 Operability Determinations (CM-1) 21

71111.19 Corrective Action 4257536 2SI8804B Mechanical and Grease Inspection 06/17/2019

Documents 4257539 2SI8912B has Inactive Packing Leak 06/17/2019

Procedures 2BwOSR Group A IST Requirements for 2B Safety Injection Pump 10

5.5.8.SI-10B (2SI01PB)

BwOP SX-1 Essential Service Water Pump Startup 23

BwOP SX-7 Swapping Essential Service Water Pumps 27

ER-AA-330-001 Section XI Pressure Testing 16

ER-AA-335-015- VT-2 Visual Examination in Accordance with ASME 2013 0

2013

Work Orders 1938834 Disassemble and Inspect 2CC070B 05/14/2019

1939833 2CC9520B Disassemble and Inspect 05/14/2019

1955970 EQ Motor Containment Spray Pump 1B 06/18/2019

4615529 1SX01AB Cooler Inspection and Cleaning 05/16/2019

4838800 Flow Indicator Containment Spray Pump Room Cooler 1B 06/18/2019

Outlet

4889939 ESF Switchgear Room Division 12 Ventilation System Vent 05/22/2019

Fan Motor

4906923 IST for 1CS003B/11B - ASME Surveillance Requirements 06/18/2019

for 1CS01PB & Check Valves

71111.22 Corrective Action 4238267 Valve Handle Not Moving Valve Stem Properly 04/10/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents 4238279 Fuel Oil Leak From Left Bank Fuel Rail 04/10/2019

238284 2PI-DG030A Turbo Air Inlet Pressure Indication is Suspect 04/10/2019

238291 2A EDG Fuel Rack Trip Level Pushbutton Fell off During 04/10/2019

EDG Run

Procedures 1BwOS MS-Q1 Main Steam Dump Valve Stroke Surveillance 11

2BwOSR 3.8.1.2- 2A Diesel Generator Operability Surveillance 47

BwOP DG-1 Diesel Generator Alignment to Standby Condition 30

BwOP DG-11 Diesel Generator Startup and Operation 51

BwOP DG-12 Diesel Generator Shutdown 30

Work Orders 4836509 2A Diesel Generator Operability Semi-Annual Surveillance 04/10/2019

4876995 Unit 1 Steam Dump Valve Quarterly Surveillance (Tave 04/11/2019

Mode and Above P-8)

4898251 2A Diesel Generator Operability Monthly Surveillance 04/10/2019

71151 Corrective Action 4236155 Unexpected Unit 2 Loose Parts Alarm 04/04/2019

Documents

Miscellaneous NRC Performance Indicator Data; Mitigating Systems - 04/01/2018 -

Safety System Functional Failures 03/31/2019

NRC Performance Indicator Data; Mitigating Systems - 04/01/2018 -

Mitigating System Performance Index for Emergency 03/31/2019

Alternating Current Power

NRC Performance Indicator Data; Mitigating Systems - 04/01/2018 -

Mitigating System Performance Index for High Pressure 03/31/2019

Injection

Procedures LS-AA-2001 Collecting and Reporting of NRC Performance Indicator 15

Data

LS-AA-2080 Monthly Data Elements for NRC Safety System Functional 7

Failures

LS-AA-2200 Mitigating System Performance Index date Acquisition and 6

Reporting

71152 Corrective Action 4209142 Unit 2 Loose Parts Alarm 01/08/2019

Documents 4210587 Unexpected Alarm, Loose Parts 01/14/2019

211151 Trend in Loose Parts Monitoring Issues 07/15/2019

212438 Unexpected Annunciator 2-13-E9, Loose Parts Monitoring 01/20/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

System Trouble

213338 Received Unexpected Annunciator 2-13-E9, Loose Parts 01/23/2019

216074 Unit 2 Loose Parts Alarm 01/31/2019

217622 Unit 1 Loose Parts Alarm 02/05/2019

219216 Unexpected Annunciator: 2-13-E9 02/12/2019

27893 Unit 2 Loose Parts Monitoring System Impact Noise Alarm 03/08/2019

Channel 4

28922 Loose Parts Alarm - Channel 1, 3, 14 - No Abnormal Noises 03/13/2019

232957 Metallic Noise Unit 1 Loose Parts Monitoring System at 1C 03/25/2019

SC Lower Narrow Range Level Tap

233318 Reactor Vessel Head Loose Parts Monitoring System Alarm 03/26/2019

Disabled 2VE-LM002

236155 Unexpected Unit 2 Loose Parts Alarm 04/04/2019

236932 Unexpected Annunciator: 2-13-EP 04/06/2019

237724 Unexpected Unit 1 Loose Parts Alarm 04/09/2019

242027 Unexpected Unit 2 Loose Parts Alarm 04/22/2019

245172 Unexpected Annunciator 1-13-E9 05/01/2019

248952 Need Work Request to Troubleshoot Unit 1 Loose Parts 05/14/2019

Monitoring System Channel 1

250626 Re-Evaluate Loose Parts Monitoring System Oversight 05/21/2019

Miscellaneous ER-AA-320-1003 Maintenance Rule 18-10 - Failure Definitions 0

Procedures BwOP LM-10 Loose Parts Monitoring System Operation and Alarm 4

Response

BwOP LM-10A1 Loose Parts Monitoring System Alignment 3

NO-AA-10 Quality Assurance Topical Report (QATR) 7

OP-AA-108-117 Protected Equipment Program 5

OP-AA-201-008 Pre-Fire Plan Manual 4

PI-AA-=125-1001 Root Cause Analysis Manual 3

PI-AA-120 Issue Identification and Screening Process 8

PI-AA-125 Corrective Action Program (CAP) Procedure 6

PI-AA-125-1003 Corrective Action Program Evaluation Manual 4

17