ML19210E060
| ML19210E060 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 07/26/2019 |
| From: | Hironori Peterson Division Reactor Projects III |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| References | |
| IR 2019002 | |
| Download: ML19210E060 (19) | |
See also: IR 05000456/2019002
Text
July 26, 2019
Mr. Bryan C. Hanson
Senior VP, Exelon Generation Company, LLC
President and CNO, Exelon Nuclear
4300 Winfield Road
Warrenville, IL 60555
SUBJECT: BRAIDWOOD STATION, UNITS 1 AND 2INTEGRATED INSPECTION
REPORT 05000456/2019002 AND 05000457/2019002
Dear Mr. Hanson:
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/
Hironori Peterson, Chief
Branch 3
Division of Reactor Projects
Docket Nos. 05000456 and 05000457
License Nos. NPF-72 and NPF-77
Enclosure:
As stated
cc: Distribution via LISTSERV
x Non-Sensitive x Publicly Available
x SUNSI Review
Sensitive Non-Publicly Available
OFFICE RIII RIII
NAME NShah:bw HPeterson
DATE 7/25/2019 7/26/2019
U.S. NUCLEAR REGULATORY COMMISSION
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: Hironori Peterson, Chief
Branch 3
Division of Reactor Projects
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
2
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.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Summer Readiness Sample (IP Section 03.01) (1 Sample)
(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) (2 Samples)
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
3
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (4 Samples)
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.) (1 Sample)
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 Sample)
(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) (1 Sample)
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
4
Routine Maintenance Effectiveness Inspection (IP Section 02.01) (2 Samples)
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) (6 Samples)
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) (6 Samples)
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
5
(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) (4 Samples)
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) (3 Samples)
(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, 2019
6
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) (2 Samples)
(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 Sample)
(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, 2019.
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.
7
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 of a NAMCO EA180 limit switch for the 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.
These switches are 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
UFSAR, Appendix A, (Page A1.89-1), For Westinghouse Nuclear Steam System Supplier
Class lE equipment, Westinghouse has met the requirements of IEEE-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
Subsequently, the licensee performed an analysis that supported the removal of seals
associated with the conduit attachment to the limit switch without affecting its environmental
qualification. The inspectors were concerned that the subsequent analysis did not align with
detailed guidance located within IEEE-323-1974.
Initially, the inspectors viewed this lack of alignment as a potential performance deficiency.
After discussions with NRR technical staff and legal staff, the inspectors determined that no
performance deficiency existed. The basis for this conclusion was that 10 CFR 50.49,
Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power
Plants, does not currently invoke any specific standard. The information contained within the
licensee's UFSAR, when viewed as a historical reference, includes information about IEEE- 323-1974 because this information describes how equipment was originally qualified.
However, the requirements pertaining to IEEE-323-1974 were sunset upon the issuance of
the Final Rule, 50.49 (see Federal Register (FR), 48 FR 2733, Jan. 21, 1983, as amended at
49 FR 45576). As a result, no performance deficiency was identified.
Corrective Action Reference(s): AR 4120790 - NRC Question on Environment Qualification
Binder Evaluation of Limit Switches
8
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.
9
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
10
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 Unit 0
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
11
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
4244974 1VA06SA Vibration Reading Results 04/30/2019
4244975 2VA06SA Vibration Reading Results 04/302019
4244994 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
4235979 Coating Repairs Needed for the 1DG01KA-X2 Lower 04/03/2019
Stationary Head
4235981 Coating Repairs Needed for the 1DG01KA-X2 Lower Pact 04/03/2019
End Channel Head
4235983 Coating Repairs Needed for the 1DG01KA-X1 Upper Pact 04/03/2019
End Channel Head
4235987 Debris Found Inside Stationary Head and Tubesheet 04/03/2019
1DG01KA-X2
4235988 Degradation Found During Inspection of 1DG01KA-X1 04/03/2019
Upper Stationary Head
4236145 Significant Amount of Oil in Air Sensing Line 04/04/2019
4236908 1A Diesel Generator South Fuel Rack Positioner Cable 04/06/2019
Broke
4236938 1A Diesel Generator Butterfly Valve Sticking 04/06/2019
4238259 1AF01PB Crankcase Oil Analysis Degrading Trend 04/10/2019
4240057 Battery Charger Lugs are Distorted on 2AF01EB-A Battery 04/16/2019
4247173 ACB 1441 Would Not Close Following SAT Restoration 05/02/2019
12
Inspection Type Designation Description or Title Revision or
Procedure Date
4247555 Ground Connections Corroded 05/08/2019
4247567 Unit 1 SAT LCO 4.0 Critique 05/08/2019
4247579 Braidwood SAT Outage Restoration Delays 05/08/2019
4248106 SAT 142-1 Received Unsatisfactory Doble Test on X3 05/10/2019
4248185 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
1 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
13
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
4920701 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
4209879 DC Bus 111 Ground Coming in with 1PL01J Panel Check 01/10/2019
4223051 1RF008 Flowrate Trend Anomaly 02/24/2019
4224618 1CV179 Cycling Excessively 02/28/2019
4228652 1RF009 Elevated Reading 03/12/2019
4229675 Unit 1 Floor Drain Sump Channel A Failed - PC002 03/15/2019
4244974 1VA06SA Vibration Reading Results 04/30/2019
4244975 2VA06SA Vibration Reading Results 04/30/2019
4244994 1VA06CD Exceeds Run Time Threshold for Motor Bearings 04/30/2019
4247579 Braidwood SAT Outage Restoration Delays 05/08/2019
4248185 DC Bus 111 Ground 05/22/2019
4249077 2HK-AF036B: Manual Loader for 2AF005G Failed - WO 05/15/2019
1893938
4253330 2SX124A is Very Difficult to Operate 05/31/2019
4254702 Erratic 2A CV Pump Cubicle Cooler SX Flow Rate 06/05/2019
14
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
15
Inspection Type Designation Description or Title Revision or
Procedure Date
Documents 4238279 Fuel Oil Leak From Left Bank Fuel Rail 04/10/2019
4238284 2PI-DG030A Turbo Air Inlet Pressure Indication is Suspect 04/10/2019
4238291 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
1
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
4211151 Trend in Loose Parts Monitoring Issues 07/15/2019
4212438 Unexpected Annunciator 2-13-E9, Loose Parts Monitoring 01/20/2019
16
Inspection Type Designation Description or Title Revision or
Procedure Date
System Trouble
4213338 Received Unexpected Annunciator 2-13-E9, Loose Parts 01/23/2019
4216074 Unit 2 Loose Parts Alarm 01/31/2019
4217622 Unit 1 Loose Parts Alarm 02/05/2019
4219216 Unexpected Annunciator: 2-13-E9 02/12/2019
4227893 Unit 2 Loose Parts Monitoring System Impact Noise Alarm 03/08/2019
Channel 4
4228922 Loose Parts Alarm - Channel 1, 3, 14 - No Abnormal Noises 03/13/2019
4232957 Metallic Noise Unit 1 Loose Parts Monitoring System at 1C 03/25/2019
SC Lower Narrow Range Level Tap
4233318 Reactor Vessel Head Loose Parts Monitoring System Alarm 03/26/2019
Disabled 2VE-LM002
4236155 Unexpected Unit 2 Loose Parts Alarm 04/04/2019
4236932 Unexpected Annunciator: 2-13-EP 04/06/2019
4237724 Unexpected Unit 1 Loose Parts Alarm 04/09/2019
4242027 Unexpected Unit 2 Loose Parts Alarm 04/22/2019
4245172 Unexpected Annunciator 1-13-E9 05/01/2019
4248952 Need Work Request to Troubleshoot Unit 1 Loose Parts 05/14/2019
Monitoring System Channel 1
4250626 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