IR 05000456/2019002
| 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: |
| References | |
| IR 2019002 | |
| Download: ML19266A637 (19) | |
Text
September 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:
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
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 018012-01 Qualification of Conduit Seal Removal for 2RY456 Limit Switch 71111.21N Closed
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
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 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:
===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) (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)===
(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 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,
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 (Closed)
Qualification of Conduit Seal Removal for 2RY456 Limit Switch 05000456,05000457/2018012-01 71111.21N
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
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
0BwOA ENV-1
Adverse Weather Conditions Unit 0
24
General Area Checks and Operator Field Rounds
OP-AA-108-107-
1001
Station Response to Grid Capacity Conditions
OP-AA-108-111-
1001
Sever Weather and Natural Disaster Guidelines
OP-BR-102-102-
1001
Augmented Operator Field Rounds
Seasonal Readiness
BwOP CS-E1
Electrical Lineup - Unit 1 Containment Spray System
Electrical Lineup
BwOP CS-M1
Operating Mechanical Lineup Unit 1
BwOP DG-E2
Electrical Lineup - Unit 1, 1B Diesel Generator
BwOP DG-M2
Operating Mechanical Lineup Unit 1, 1B Diesel Generator
Fire Plans
No. 104; Fire
Zone 11.2A-2
Auxiliary Building 364' Elevation RHR Pump 2A Room
No. 114; Fire
Zone 11.3-1
Auxiliary Building 364' Elevation Unit 1 Containment Pipe
Penetration Area
No. 104; Fire
Zone 11.2A-2
Auxiliary Building 364' Elevation Residual Heat Removal
Pump 2A Room
No. 114; Fire
Zone 11/3-1
Auxiliary Building 364' Elevation Unit 1 Containment Pipe
Penetration Area
No. 178; Fire
Zone 12.1-0
Fuel Handling Building 401' Elevation
No. 179; Fire
Zone 12.1-0
Fuel Handling Building 426' Elevation
No. 200; Fire
Zone 18.2-2
Auxiliary Building 401' Elevation Diesel Generator 2A &
Switchgear Room Air Shaft
Procedures
BwAP 1110-1
Fire Protection Program System Requirements
BwAP 1110-3
Plant Barrier Impairment Program
BwOP PBI-1
Plant Barrier Control Program
Plant Barrier Control Program
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
High Risk Fire Area Identification
ER-BR-600-1069
Site List of High Risk Fire Areas - Braidwood Unit 1 and
Unit 2
Fire Prevention for Hot Work
Fire Protection System Impairment Control
Control of Transient Combustible Material
0BwOA PRI-8
Auxiliary Building Flooding Unit 0
BwAP 1110-3
Plant Barrier Impairment Program
BwOP PBI-1
Plant Barrier Impairment Program Pre-Evaluated Barrier
Matrix
Plant Barrier Control Program
Risk Management
OP-11-101-113-
1006
4.0 Crew Critique Guidelines
OP-AA-101-111-
1001
Operations Standards and Expectations
Operator Fundamentals
Watch Standing Practices
OP-AA-103-102-
1001
Strategies for Successful Transient Mitigation
Operation of Plant Equipment
Communications
OP-AA-108-107-
1002
Interface Procedure Between BGE/COMED/PECO and
Exelon Generation (Nuclear/Power) for Transmission
Operations
Operating Narrative Logs and Records
Reactivity Management
Systematic Approach to Training Process Description
Operator Training Programs
Conduct of Simulator Training and Evaluation
Examination Security and Administration
Simulator Management
TQ-BR-201-0113
Braidwood Training Department Simulator Examination
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Security Actions
Corrective Action
Documents
0881124
Long Range Planning for 1VA06CD Motor Refurbishment
2/16/2009
238259
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
Maintenance Rule Functions - Safety Significant
Classification
Maintenance Rule Implementation per NEI 18-10
Maintenance Rule 18-10 - Scoping
Maintenance Rule 18-10 - Performance Monitoring and
Dispositioning Between (a)(1) and (a)(2)
Calculations
BRW-97-0340-E
Battery Duty Cycle and Sizing for the Braidwood Diesel
Driven Auxiliary Feedwater Pumps
Corrective Action
Documents
2667064
Lessons Learned - Unit 1 System Auxiliary Transformer
(SAT) Outage Temporary State Estimator Alarm Setpoint
05/09/2016
235979
Coating Repairs Needed for the 1DG01KA-X2 Lower
Stationary Head
04/03/2019
235981
Coating Repairs Needed for the 1DG01KA-X2 Lower Pact
End Channel Head
04/03/2019
235983
Coating Repairs Needed for the 1DG01KA-X1 Upper Pact
End Channel Head
04/03/2019
235987
Debris Found Inside Stationary Head and Tubesheet
1DG01KA-X2
04/03/2019
235988
Degradation Found During Inspection of 1DG01KA-X1
Upper Stationary Head
04/03/2019
236145
Significant Amount of Oil in Air Sensing Line
04/04/2019
236908
1A Diesel Generator South Fuel Rack Positioner Cable
Broke
04/06/2019
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
Procedure
Type
Designation
Description or Title
Revision or
Date
247555
Ground Connections Corroded
05/08/2019
247567
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
248185
Direct Current Bus 111 Ground
05/11/2019
Engineering
Evaluations
20474
Evaluation of Single SAT Operation on Unit 1 for 2019
Procedures
1BwOSR 3.8.1.1
Unit 1 Offsite AC Power Availability Surveillance
2BwHS 384-6
Volt ESF Auxiliary Feed Diesel Battery BT2 and BT2
Performance Test
2BwHSR 3.7.5-
BA
2B Diesel Auxiliary Feed Pump Battery Bank B Battery A
(2AF01EB-A) Capacity Test
2BwOS DC-Q4
24V DC Auxiliary Feed Pump 2B Battery Bank A and B
Quarterly Surveillance
BwHP 4006-023
Bus Disconnect Link Relocation on 6900 V SAT Buses
BwHP 4006-059
Operation of the Biddle/AVO Ground Fault Tracer
BwHP 4006-066
DC Bus Ground Location Using the Multi-Amp Battery
Ground-Fault Locator
BwHP 4006-074
Bus Disconnect Link Relocation on 4160 V SAT Buses
BwHS 4002-084
System Auxiliary Transformer Preventative Maintenance
Inspection
BwMP 3100-022
Diesel Generator 2 Year Inspection
BwMP 3200-014
Auxiliary Feedwater Pump Diesel Drive Unit Inspection and
Maintenance
BwOP AP-15
Isolating System Auxiliary Transformer (SAT) 142-1 with Unit
Unit Auxiliary Transformer (UAT) Energized
BwOP AP-20
Restoring System Auxiliary Transformer (SAT 142-2) with
Unit 1 UAT Energized
BwOP AP-54
With SAT 142-1 Isolated, Isolate SAT 142-2 and Restore
SAT 142-1 with Unit 1 UAT Energized
BwOP DC-E2
Electrical Lineup - Unit 1 Operating - 125 Vdc Division 11
ASME Section XI Repair/Replacement Program
ER-AA-335-015-
VT-2 Visual Examination in Accordance with ASME 2013
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2013
On-Line Risk Management
MA-AA-716-230-
1004
Lubricant Sampling Guideline
MA-BR-EM-4-
09070
Diesel Generator Electrical Inspection
Protected Equipment Program
On-Line Risk Management and Assessment
Integrated Risk Management
Work Orders
1836579
Volt Auxiliary Feed Battery Bank Capacity Test
(2AF01EB)
04/15/2019
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
Corrective Action
Documents
2667064
Lessons Learned - Unit 1 SAT Outage Temporary State
Estimator Alarm Setpoint
09/09/2016
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
2/24/2019
24618
1CV179 Cycling Excessively
2/28/2019
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 1893938
05/15/2019
253330
2SX124A is Very Difficult to Operate
05/31/2019
254702
Erratic 2A CV Pump Cubicle Cooler SX Flow Rate
06/05/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Changes
Performance of Cubicle Coolers 1VA06SA and 2VA06SA
with One or Two Fans in Operation
Procedures
1BwOS DC-1a
AAR-125 Vdc ESF Bus Ground
BwOL 3.8.4
LCOAR
DC Sources - Operating Technical Specification LCO 3.8.4
BwOP DC-23-111 125 Vdc Bus 111/113 Ground Detection
Administrative Requirements for Inservice Testing
Risk Management Documentation
Risk Assessments of Missed or Deficient Surveillances
OP-AA-106-101-
1006
Operational Decision Making Process
Adverse Condition Monitoring and Contingency Planning
Operability Determinations (CM-1)
Corrective Action
Documents
257536
2SI8804B Mechanical and Grease Inspection
06/17/2019
257539
2SI8912B has Inactive Packing Leak
06/17/2019
Procedures
2BwOSR
5.5.8.SI-10B
Group A IST Requirements for 2B Safety Injection Pump
(2SI01PB)
BwOP SX-1
Essential Service Water Pump Startup
BwOP SX-7
Swapping Essential Service Water Pumps
Section XI Pressure Testing
ER-AA-335-015-
2013
VT-2 Visual Examination in Accordance with ASME 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
Outlet
06/18/2019
4889939
ESF Switchgear Room Division 12 Ventilation System Vent
Fan Motor
05/22/2019
4906923
IST for 1CS003B/11B - ASME Surveillance Requirements
for 1CS01PB & Check Valves
06/18/2019
Corrective Action
238267
Valve Handle Not Moving Valve Stem Properly
04/10/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
238279
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
EDG Run
04/10/2019
Procedures
1BwOS MS-Q1
Main Steam Dump Valve Stroke Surveillance
2BwOSR 3.8.1.2-
2A Diesel Generator Operability Surveillance
BwOP DG-1
Diesel Generator Alignment to Standby Condition
BwOP DG-11
Diesel Generator Startup and Operation
BwOP DG-12
Diesel Generator Shutdown
Work Orders
4836509
2A Diesel Generator Operability Semi-Annual Surveillance
04/10/2019
4876995
Unit 1 Steam Dump Valve Quarterly Surveillance (Tave
Mode and Above P-8)
04/11/2019
4898251
2A Diesel Generator Operability Monthly Surveillance
04/10/2019
71151
Corrective Action
Documents
236155
Unexpected Unit 2 Loose Parts Alarm
04/04/2019
Miscellaneous
NRC Performance Indicator Data; Mitigating Systems -
Safety System Functional Failures
04/01/2018 -
03/31/2019
NRC Performance Indicator Data; Mitigating Systems -
Mitigating System Performance Index for Emergency
Alternating Current Power
04/01/2018 -
03/31/2019
NRC Performance Indicator Data; Mitigating Systems -
Mitigating System Performance Index for High Pressure
Injection
04/01/2018 -
03/31/2019
Procedures
Collecting and Reporting of NRC Performance Indicator
Data
Monthly Data Elements for NRC Safety System Functional
Failures
Mitigating System Performance Index date Acquisition and
Reporting
Corrective Action
Documents
209142
Unit 2 Loose Parts Alarm
01/08/2019
210587
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
Procedure
Type
Designation
Description or Title
Revision or
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
2/05/2019
219216
Unexpected Annunciator: 2-13-E9
2/12/2019
27893
Unit 2 Loose Parts Monitoring System Impact Noise Alarm
Channel 4
03/08/2019
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
SC Lower Narrow Range Level Tap
03/25/2019
233318
Reactor Vessel Head Loose Parts Monitoring System Alarm
Disabled 2VE-LM002
03/26/2019
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
Monitoring System Channel 1
05/14/2019
250626
Re-Evaluate Loose Parts Monitoring System Oversight
05/21/2019
Miscellaneous
Maintenance Rule 18-10 - Failure Definitions
Procedures
BwOP LM-10
Loose Parts Monitoring System Operation and Alarm
Response
BwOP LM-10A1
Loose Parts Monitoring System Alignment
Quality Assurance Topical Report (QATR)
Protected Equipment Program
Pre-Fire Plan Manual
PI-AA-=125-1001
Root Cause Analysis Manual
Issue Identification and Screening Process
Corrective Action Program (CAP) Procedure
Corrective Action Program Evaluation Manual
4