IR 05000456/2019004
| ML20027B437 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 01/24/2020 |
| From: | Hironori Peterson NRC/RGN-III |
| To: | Bryan Hanson Exelon Generation Co |
| References | |
| EA-16-126 IR 2019004 | |
| Preceding documents: |
|
| Download: ML20027B437 (31) | |
Text
January 24, 2020
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000456/2019004 AND 05000457/2019004
Dear Mr. Hanson:
On December 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Braidwood Station, Units 1 and 2. On January 9, 2020, 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.
No NRC-identified or self-revealing findings were identified during this inspection.
A licensee-identified violation which was determined to be of very low safety significance is documented in this report. We are treating this violation as a non-cited violation (NCV)
consistent with Section 2.3.2 of the Enforcement Policy.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Hironori Peterson, Chief Branch 3 Division of Reactor Projects
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:
05000456/2019004 and 05000457/2019004
Enterprise Identifier: I-2019-004-0058
Licensee:
Exelon Generation Company, LLC
Facility:
Braidwood Station, Units 1 and 2
Location:
Braceville, IL
Inspection Dates:
October 01, 2019 to December 31, 2019
Inspectors:
R. Bowen, Illinois Emergency Management Agency
J. Bozga, Senior Reactor Inspector
J. Corujo-Sandin, Senior Resident Inspector
G. Edwards, Health Physicist
T. Go, Health Physicist
D. Kimble, Senior Resident Inspector
C. Phillips, Project Engineer
M. Porfirio, Illinois Emergency Management Agency
P. Smagacz, Resident Inspector
L. Torres, Illinois Emergency Management Agency
Approved By:
Hironori Peterson, Chief
Branch 3
Division of Reactor Projects
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. A licensee-identified non-cited violation is documented in report section: 71111.05Q.
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 05000456,05000457/20 18011-01 Installed Plant Equipment Protection Against Tornado 71111.15 Closed EDG EA-16-126 Closure of EA-16-126 and Associated Enforcement Discretion Regarding Tornado Missiles Protection 71111.15 Closed
PLANT STATUS
Unit 1 began the inspection period operating at approximately 90 percent power with end-of-cycle power coast down operations in progress. On October 7, 2019, the unit was shut down for its planned 21st refueling outage (A1R21). Following completion of refueling and other maintenance activities, the reactor was restarted and taken critical on October 22, 2019, and the main electrical generator was synchronized to the power grid later that same day. The unit reached full power operation on October 27, 2019, and with the exception of minor reductions in power to support scheduled testing activities and load changes requested by the transmission system dispatcher, the unit remained operating at or near full power for the remainder of the 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 and 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
Seasonal Extreme Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures during the weeks ending November 9, through December 21, 2019
External Flooding Sample (IP Section 03.04) (1 Sample)
- (1) The inspectors evaluated the licensee's readiness to cope with external flooding during the week ending December 7, 2019
71111.04Q - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations and conducted selected alignment verifications on the following systems/equipment trains that were important to safety:
- (1) The 1A Safety Injection (SI) Train while it was being credited as a mitigation system during reduced Reactor Coolant System (RCS) inventory operations during the week ending October 12, 2019
- (2) The pre-staged FLEX equipment to support Unit 1 shutdown safety during reactor refueling cavity draindown and RCS reduced inventory operations during the weeks ending October 19 through October 26, 2019
- (3) The 1B Auxiliary Feedwater (AF) Train while the 1A AF Train was undergoing maintenance during the week ending November 2, 2019
- (4) The Unit 1 and Unit 2 Essential Service Water (SX) systems while the 2B SX Pump was undergoing scheduled maintenance during the week ending November 23, 2019
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (5 Samples)
The inspectors assessed fire protection program implementation for the issues noted and/or in the following selected plant areas:
- (1) The Unit 1 Missile Shield Area, Containment 377' - 0" Elevation, Fire Zone 1.1-1 during the week ending October 12, 2019
- (2) The Unit 1 Missile Shield Area, Containment 401' - 0" Elevation, Fire Zone 1.1-1 during the week ending October 19, 2019
- (3) The Unit 1 Containment Annular Area, Containment 401' - 0", Fire Zone 1.1-1 during the week ending October 19, 2019
- (4) The Unit 1 Diesel AF Pump Room, Auxiliary Building 383' Elevation, Fire Zone 11.4A-1 during the week ending November 2, 2019
- (5) A missed compensatory fire watch for an out of service automatic CO2 fire suppression system in the Unit 2 Lower Cable Spreading Room on November 15, 2019
71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)
- (1) The inspectors verified that the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from October 7, 2019 to October 17 2019:
03.01.a - Nondestructive Examination and Welding Activities.
- Ultrasonic (UT) examination of main steam system pipe to elbow weld 1-MS-02-24
- UT examination of main steam system elbow to pipe weld 1-MS-02-25
- UT examination of main steam system pipe to elbow weld 1-MS-02-26
- UT examination of main steam system elbow to pipe weld 1-MS-02-27
- UT examination of main steam system pipe to elbow weld 1-MS-02-28
- UT examination of main steam system elbow to pipe weld 1-MS-02-29
- UT examination of main steam system elbow to pipe weld 1-MS-02-32
- UT examination of reactor coolant pipe 1RC14AA
- UT examination of reactor coolant pipe 1RC14AB
- UT examination of reactor coolant pipe 1RC14AC
- UT examination of reactor coolant pipe 1RC14AD
- UT examination of containment spray system pipe to elbow weld 1-CS-03-76
- UT examination of containment spray system elbow to pipe weld 1-CS-03-77
- UT examination of reactor coolant pump main flange bolts 1-RCP-01-RCP-PD-01 to 24
- General Visual Examination (GV) of IWE Containment Liner Surfaces:
Elevation 426'-0" OMB
- Visual Examination (VT-3) of snubber support 1RC02006BS
- VT-3 of snubber support 1RC02006AS
- Visual examination for leakage (VT-2) of 1RC14AA
- Visual examination for leakage (VT-2) of 1RC14AB
- Visual examination for leakage (VT-2) of 1RC14AC
- Visual examination for leakage (VT-2) of 1RC14AD
03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities.
- Bare Metal Visual (BMV) examination of the reactor vessel upper head penetrations;
- Liquid Penetrant (PT) examination of embedded flaw repair on the reactor vessel head, Control Rod Drive (CRD) Nozzle 69
03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.
- Boric Acid Leakage Evaluation on Component ID 1SI121B
- Boric Acid Leakage Evaluation on Component ID 1CS020A
- Corrective Actions to Leakage at 1CV8396B (WO 04775229-01)
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the Main Control Room during various activities, including Unit 1 shutdown for Refueling Outage A1R21 and subsequent restart during the weeks ending October 5 through October 26, 2019
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness Inspection (IP Section 02.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance activities associated with the following equipment and/or safety significant functions:
- (1) The 0B Control Room Heating, Ventilation and Air Conditioning Chiller/Train maintenance during the weeks ending November 23 through December 7, 2019
- (2) The 1B EDG maintenance during the weeks ending December 21 through December 28, 2019
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (2 Samples)
The inspectors reviewed and evaluated the licensee's assessment of plant risk for the following work activities:
- (1) Emergent work associated with the 1C Steam Generator (SG) Power Operated Relief Valve (PORV) (1MS018C) as documented in Issue Report (IR) 4293122 during the weeks ending November 2 through November 23, 2019
- (2) Emergent work associated with the 1A SG PORV (1MS018A) as documented in IR 4297820 during the weeks ending November 23, through November 30, 2019
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 02.02) (3 Samples)
The inspectors evaluated the following licensee operability determinations:
- (1) Closure of EA-16-126 and the associated Enforcement Discretion regarding protection against tornado missiles during the weeks ending October 12 through November 2, 2019
- (2) Evaluation of 1A AF Pump operability following issues identified during testing as documented in IR 4285855 during the weeks ending October 12 through October 19, 2019
- (3) Evaluation of 2B EDG operability following observation of jacket water system pressure surges during testing as documented in IR 4298842 during the weeks ending November 23 through November 30, 2019
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)
The inspectors evaluated the following permanent modifications and/or changes to the facility:
- (1) Changes to the operation of the AF system to support a loss of normal feedwater during a unit startup as documented in Engineering Change (EC) 627959 during the weeks ending October 5 through December 7, 2019
- (2) Enhancements to the existing Unit 1 digital control system (Westinghouse Ovation) as documented in EC 625405 during the weeks ending October 19 through December 7, 2019
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)
The inspectors reviewed and evaluated the following post maintenance testing activities:
- (1) The Unit 1 core alignment verification following reactor refueling as documented in Work Order (WO) 4775529 during the week ending October 19, 2019
- (2) Operability testing of the 1B EDG following maintenance as documented in WO 4751478 during the week ending October 19, 2019
- (3) Testing of the 1A Charging (CV) Pump following maintenance as documented in WO 4751462 during the weeks ending October 19 through October 26, 2019
- (4) Unit 1 digital rod position indication (DRPI) operability checks following reactor refueling as documented in WO 4781082 during the week ending October 26, 2019
- (5) Unit 1 control rod drop time testing following reactor refueling as documented in WO 4820752 during the week ending October 26, 2019
- (6) Functional testing of the of 0B VC Ventilation Train/Chiller following guide vane replacement as documented in WO 1929795 during the week ending November 30, 2019
- (7) Operability testing of the 1B EDG following maintenance as documented in WO 4798246 during the week ending December 28, 2019
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors reviewed and evaluated Unit 1 Refueling Outage A1R21 activities from October 12 through October 26, 2019
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance testing activities:
Surveillance Tests (other) (IP Section 03.01)
(1)1BwOSR 3.3.2.9-2: Unit 1 - Train B SI manual initiation and Phase "A" Containment Isolation manual initiation surveillance during the week ending October 12, 2019 (2)2BwOSR 3.8.1.13-1: 2A EDG bypass of automatic trips surveillance during the week ending November 9, 2019
Inservice Testing (IP Section 03.01) (2 Samples)
- (1) BwMP 3305-003: Main Steam Safety Valve testing using a setpoint verification device during the weeks ending October 5 through October 12, 2019 (2)1BwOSR 5.5.8.AF-4A: Unit 1 comprehensive inservice testing requirements for AF pumps during the weeks ending October 5 through October 12, 2019
Containment Isolation Valve Testing (IP Section 03.01) (2 Samples)
(1)1BwOSR 3.6.1.1-17: Primary Containment Type C local leakage rate tests for the make-up demineralizer system during the weeks ending October 19 through October 26, 2019
- (2) The overall fuel cycle test results and summation of Unit 1 Primary Containment Type B and Type C local leak rates as documented in WO 4821955 during the week ending November 2, 2019
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)
The inspectors evaluated the site's emergency response organization during observation of the following drill activity:
- (1) A graded emergency scenario for a crew of licensed operators in the station's control room simulator on November 15,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 02.01) (1 Sample)
The inspectors evaluated radiological hazards assessments and controls.
- (1) The inspectors reviewed the following:
Radiological Surveys
- Containment 377' A1R21 Shutdown
- Containment 390' A&D Steam Generator Platform
- Containment 390' B&C Steam Generator Platform
- Containment 401' Inside Missile Barrier
- Containment 426' Lower Cavity Survey
- Containment 410' Seal Table Area
Risk Significant Radiological Work Activities
- Seal Table Activities
- Under-vessel Activities Incore Sump
- Reactor Head and Upper Internal
Air Sample Survey Records
- Seal Table activities on Unit-1 401'
- Upper Internal and Reactor Head Activities on Unit-1 426'
- Lower Cavities on Unit-1 426'
Instructions to Workers (IP Section 02.02) (1 Sample)
The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas.
- (1) The inspectors reviewed the following:
Radiation Work Packages
- BW-01-19-00619; Undervessel Activities Incore Sump
- BW-01-19-00614; Reactor Head and Upper Internals Move
- BW-01-19-00649; Seal Table Room Outage Activities
- BW-01-19-00613; Reactor Head Disassembly/Reassembly
Electronic Alarming Dosimeter Alarms
- There were no electronic dosimeter alarms available for review during this inspection.
Labeling of Containers
- Three or More Plastic Bags Containing Dry Active Waste (DAW) in Radwaste 401' Facility
- Multiple Bags Containing DAW at the Upper and Lower Containment
Contamination and Radioactive Material Control (IP Section 02.03) (1 Sample)
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.
- (1) The inspectors verified the following sealed sources are accounted for and are intact:
- J.L. Shepherd Model 89 Calibrator Containing 400 Ci of Cs-137 S.N.
BWS-106i
- J.L. Shepherd Model 89 Calibrator Containing 2nd Source of 130 mCi of Cs-137 S.N. BWS-105i
- AmBe Sealed Source in Shape of a Sphere Containing 5Ci Am-241/Beryllium S.N. BWS-102
- Neutron Calibrator Containing 65 mCi of Cf-252 S.N. BWS-104i
Radiological Hazards Control and Work Coverage (IP Section 02.04) (1 Sample)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.
- (1) The inspectors also reviewed the following radiological work package for areas with airborne radioactivity:
- BW-01-19-00619; Under-vessel Activities Incore Sump
- BW-01-19-00614; Reactor Head and Upper Internals Move
- BW-01-19-00649; Seal Table Room Outage Activities
- BW-01-19-00613; Reactor Head Disassembly/Reassembly High Radiation Area and Very High Radiation Area Controls (IP Section 02.05) (1 Sample)
- (1) The inspectors evaluated risk-significant high radiation area and very high radiation area controls.
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 02.06) (1 Sample)
- (1) The inspectors evaluated radiation worker performance and radiation protection technician proficiency.
71124.02 - Occupational ALARA Planning and Controls
Radiological Work Planning (IP Section 02.01) (1 Sample)
The inspectors evaluated the licensees radiological work planning.
- (1) The inspectors reviewed the following activities:
- BW-01-19-00649; Seal Table Room Outage Activities
- BW-01-19-00619; Under-vessel Activities
- BW-01-19-00613; Reactor Head Disassembly/Reassembly
- BW-01-19-00614; Reactor Head and Upper Internal Move
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment
Instrumentation and Equipment (IP Section 02.04) (1 Sample)
The inspectors reviewed the following radioactive effluent discharge system surveillance test results:
- (1) Auxiliary Building Ventilation Test of Nuclear-Grade Activated Carbon
71124.08 - Radioactive Solid Waste Processing and Radioactive Material Handling, Storage,
and Transportation
Radioactive Material Storage (IP Section 02.01)
The inspectors evaluated radioactive material storage.
- (1) The inspectors toured the following areas:
- Sea Vans Located and Stored Within the Protected Area
- Radioactive Waste Storage/Processing Area (Various Locations)
- Auxiliary Building (Various Locations)
The inspectors performed a container check (e.g., swelling, leakage and deformation)on the following containers:
- Filter Drum 0AB02FA
- Filter Drum 0AB02FB
- Filter Drum 1FC02F
- Filter Drum 0AB02FA
- Filter Drum 0AB02FB
Radioactive Waste System Walkdown (IP Section 02.02) (1 Sample)
The inspectors evaluated the following radioactive waste processing systems and processes during plant walkdowns:
- (1) Liquid or Solid Radioactive Waste Processing Systems
- Advanced Liquid Processing System (ALPS) Located in the Radioactive Waste Area
- Reverse Osmosis Water Processing Equipment Located in the Radioactive Waste Area
Radioactive Waste Resin and/or Sludge Discharges Processes
- Vendor Conducted Resin Sluicing Into an Onsite Liner
Waste Characterization and Classification (IP Section 02.03) (1 Sample)
The inspectors evaluated the radioactive waste characterization and classification for the following waste streams:
(1)
- 2018 Radwaste Resin Stream 10 CFR 61 Database Analysis
Shipment Preparation (IP Section 02.04) (1 Sample)
The inspectors evaluated the following radioactive material shipment preparation processes:
- (1) RWS19-003; UN2916, Radioactive Material, Type B(U) Package, 7; 0W05T Resin Liner PO676656-19 in Cask RT-100 #3
-This sample supplements inspection activities that were documented in integrated report 2019001. This constitutes one complete sample.
Shipping Records (IP Section 02.05) (1 Sample)
The inspectors evaluated the following non-excepted package shipment records:
(1)
- RWS19-018; UN3321, Radioactive Material, Low Specific Activity (LSA-II), 7; 20' Shielded DAW Sealand
- RWS19-003; UN2916, Radioactive Material, Type B(U) Package, 7; 0W05T Resin Liner PO676656-19 in Cask RT-100 #3
- RWS19-004; UN2916, Radioactive Material, Type B(U) Package, 7, 0W05T Resin Liner PO676656-13 in Cask RT-100 #3
- RWS19-012; UN2910, Radioactive Material, Excepted Package - Limited Quantity of Material,
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicator information through the selected review of the submittal information listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10)===
- (1) Unit 1 RCS Specific Activity Samples (March 2018 through June 2019)
- (2) Unit 2 RCS Specific Activity Samples (March 2018 through June 2019)
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 1 (October 1, 2018 through September 30, 2019)
- (2) Unit 2 (October 1, 2018 through September 30, 2019)
PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
- (1) Radiological Effluent Occurrences Samples (July 2018 through July 2019)
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program and other work documentation for potential adverse trends associated with alternating current (AC)circuit breaker trip testing during the A1R21 refueling outage during the weeks ending December 21 through December 31, 2019
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)
The inspectors performed an in-depth review of the licensees corrective actions for the following issue:
- (1) The need for the 1C SG Feedwater Regulating Valve (1FW530) to be operated in the fully open position following power ascension after the A1R21 refueling outage, as documented in IR 4291137 during the weeks ending December 21 through December 31, 2019
71153 - Followup of Events and Notices of Enforcement Discretion Event Followup (IP Section 03.01)
- (1) The inspectors reviewed and evaluated the licensee's response to the inadvertent actuation of emergency plan sirens as documented in NRC Event Notification54360 during the week ending November 2,
INSPECTION RESULTS
Licensee-Identified Non-Cited Violation 71111.05Q This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Technical Specification (TS) Section 5.4.1.c requires that written procedures be established, implemented, and maintained for activities associated with the implementation of the sites Fire Protection Program. One of several procedures established by the licensee to meet this requirement was BwAP 1110-1A4, GOCAR [General Operation Condition Action Requirement] Required Compensatory Measures Action Response Carbon Dioxide Fire Suppression Systems. Revision 10 of this procedure, which was the revision active and in effect on November 15, 2019, required that a continuous fire watch be established and maintained for Fire Zone 2S-43 within the Unit 2 Lower Cable Spreading Room when the carbon dioxide suppression system associated with that fire zone was not operable.
Contrary to this requirement, on November 15, 2019, the licensee failed to implement the compensatory continuous fire watch as required by TS Section 5.4.1.c and BwAP 1110-1A4, Revision 10. Specifically, a communications error between the on-shift Operations crew and craft personnel resulted in the inadvertent securing of the continuous fire watch for Fire Zone 2S-43 for approximately 53 minutes while the carbon dioxide suppression system associated with that fire zone was not operable.
Significance/Severity: Green. The inspectors assessed the significance of the finding using Inspection Manual Chapter (IMC) 0609, Appendix F, Attachment 1, Fire Protection Significance Determination Process Worksheet, dated May 2, 2018. In accordance with Step 1.5 of this document, a Senior Reactor Analyst (SRA) reviewed the licensee's risk evaluation and verified the core damage frequency results were significantly less than the 1E-6/year threshold (Green).
Corrective Action References: Issue Report (IR) 42977714, Plant Barrier Impairment, BwAP 1110-1A4 Fire Watch Communication Issue
Unresolved Item (Closed)
Installed Plant Equipment Protection Against Tornado URI 05000456,05000457/2018011-01 71111.15
Description:
This Unresolved Item (URI) was identified while performing Temporary Instruction (TI)2515/191, Mitigating Strategies, Spent Fuel Pool Instrumentation and Emergency Preparedness (ML18033A711). The inspectors questioned whether the installed plant equipment which was nonconforming to the current licensing basis for protection against tornado-generated missiles, and is relied upon to implement the mitigating strategies, met the requirements of Order EA-12-049 for reasonable protection from external events.
Specifically, the inspectors were concerned about non-conforming structures, systems or components which the licensee had identified in their corrective action program (AR 2673854).
At the time of the inspection the licensee had invoked EGM 15-002, Enforcement Discretion for Tornado-Generated Missile Protection Non-compliance, which allowed the NRC to exercise enforcement discretion when an operating power plant does not comply with its current licensing basis for tornado-generated missile protection. Inspectors had previously documented the exercise of enforcement discretion in inspection reports 2016-002 (ML16209A139) and 2017-001 (ML17121A339). Enforcement Action (EA) number, EA-16-126, was tracking the use of the enforcement discretion until final corrective actions were implemented.
As discussed in the Enforcement Discretion section of this report, final corrective actions regarding EA-16-126 have been completed. The affected structures, systems and components were restored to compliance with their tornado-generated missile licensing bases. As a result, URI 05000456,05000457/2018011-01 is considered closed.
Corrective Action Reference(s): AR 04109224 - "NRC URI - Tornado Missile Protection for Installed Equipment" AR 02673854 - "Non-Conforming Conditions Identified - Tornado Missiles"
Enforcement Discretion Enforcement Action EA-16-126: Closure of EA-16-126 and Associated Enforcement Discretion Regarding Tornado Missiles Protection 71111.15
Description:
On June 10, 2015, the NRC issued Regulatory Issue Summary (RIS) 2015-06, Tornado Missile Protection, (ML15020A419) and Enforcement Guidance Memorandum (EGM) 15-002, "Enforcement Discretion for Tornado-Generated Missile Protection Noncompliance" (ML15111A269). The RIS focused on the requirements regarding tornado-generated missile protection and required compliance with the facility-specific licensing basis. The EGM provided guidance to allow the NRC staff to exercise enforcement discretion when an operating power plant licensee did not comply with the current license basis for tornado-generated missile protection.
On May 25, 2016, the licensee documented several identified non-conformances related to tornado missile protection in their corrective action program (AR 02673854). In addition, the licensee discussed their intent to request to use the enforcement discretion, afforded by EGM 15-002, and discussed the actions required to comply with the provisions in the EGM.
Inspectors documented the exercise of enforcement discretion in the baseline quarterly reports 2016-002 (ML16209A139) and 2017-001 (ML17121A339). Enforcement Action (EA)number, EA-16-126, was assigned to administratively track the use of enforcement discretion until final corrective actions were implemented.
Corrective Actions: By letter dated February 1, 2018, (ML18036A227), as supplemented by letters dated July 9, 2018, (ML18036A227) and August 3, 2018, (ML18215A421) the licensee submitted a license amendment request to revise their licensing bases regarding protection from tornado-generated missiles. As part of the amendment process the licensee committed to protecting the reactor water storage tanks (RWSTs) hatches from tornado-generated missiles. The licensee installed the committed physical protection via Engineering Change 618920, Tornado Missile Protection for Refueling Water Storage Tank Roof Hatches.
On November 8, 2018, the NRC issued license amendment No. 199 to NPF-72, amendment No. 199 to NPF-77 and its associated safety evaluation report (ML18291A980). Based on its evaluation the NRC approved Braidwood Station, Units 1 and 2, to revise the Updated Final Safety Analysis Report (UFSAR) to incorporate the TORMIS computer Code as the methodology used for assessing tornado-generated missile protection of specific unprotected plant structures, systems and components and to describe the results of the site-specific tornado hazard analysis as described in the licensees application and safety evaluation.
Corrective Action References: AR 02673854 - "Non-Conforming Conditions Identified - Tornado Missiles" AR 04014784 - "1Q17 LIV - Lack of Adequate Tornado Missile Protection" AR 04217133 - "DBAI - Global Effects of Missile Impact on RWST Hatch Cover"
Enforcement:
Based on the licensees corrective actions described above no additional violations were identified, the enforcement discretion afforded by EGM 15-002 is no longer required and EA-16-126 is considered closed.
The disposition of this issue closes URI: 05000456,05000457/2018011-01.
Observation: Steam Generator 1C Main Feedwater Regulating Valve, 1FW530, Required to be Operated in the Fully Open Position 71152 The inspectors performed a detailed review of IR 4291137, 1FW530 Full Open Following Power Ascension. The issue involved the need for the licensee to operate the 1C Steam Generator (SG) Main Feedwater Regulating Valve (FRV), 1FW530, in the fully open position to provide adequate feedwater flow to the 1C SG at full power following return of Unit 1 to operation after the licensees October 2019 A1R21 refueling outage. This condition stemmed from the fact that the associated main feedwater check valve in that line, 1FW079C, did not open to the expected position for the full power operating condition and additional open travel on 1FW530 was required to compensate for the additional flow resistance in the line.
The failure of the 1FW079C check valve to move to the expected open position for full power operation appears to be a design issue associated with the FW079 series check valves in the stations main feedwater lines. Similar issues have been observed from time to time by the licensee with various FW079 series check valves going back a number of years. In 2018 when an analogous condition occurred on the 1B SG main feedwater line, the inspectors reviewed the licensees operability and functionality evaluation for the 1FW079B check valve being more closed than expected for the full power operating condition and did not identify any findings or violations of NRC requirements. (Reference: Braidwood Station, Units 1 and 2 - NRC Integrated Inspection Report 05000456/2018003 and 05000457/2018003; ADAMS Accession Number: ML18304A205). Consequently, for this detailed Problem Identification and Resolution inspection sample, the inspectors focused on assessment of the licensees corrective actions taken to date and those planned going forward.
At Braidwood Stations sister facility, Byron Station, the licensee replaced the FW079 series main feedwater check valves several years ago with check valves of a different design in order to alleviate the condition at that facility. In reviewing the licensees corrective actions for this most recent condition at Braidwood Station, the inspectors noted that one of the actions within the licensees corrective action program (CAP) tasked licensees engineering organization with evaluating the modification performed at Byron Station for potential use at Braidwood. In addition, the licensee established corrective actions to evaluate possibly increasing the speed of the running turbine-driven main feedwater pumps to force the 1C SG FRV to close somewhat. This, however, would also impact the other three Unit 1 FRVs, which are presently operating as desired. Lastly, the licensee has developed an adverse condition monitoring plan in accordance with station procedures and processes to monitor the condition, with trigger points for additional analysis and/or actions should the condition degrade.
The FRVs are intended to be able to modulate to adjust SG level as necessary during plant operation. The overall safety significance of the issue comes down to an increased risk of SG level instability if a second Unit 1 FRV were to reach the fully open position with 1FW530 already needing to be fully open to ensure proper main feedwater flow to the 1C SG.
Following their review, the inspectors concluded that the licensees actions taken in accordance with their CAP were reasonable given the overall safety significance of the issue.
The inspectors did not identify any findings or violations of NRC requirements in the course of their review.
Observation: Potential Trend in Molded Case Circuit Breaker Trip Testing Issues 71152 The inspectors performed a review of plant issues, particularly those entered into the licensees corrective action program (CAP), associated with problems encountered during MCCB trip testing that was accomplished as part of the licensees Unit 1 A1R21 refueling outage. During their review, the inspectors noted that there had been several MCCB testing issues encountered by the licensee. In each of the six cases noted, the subject MCCB was subsequently evaluated as being capable of adequately tripping if required. Four of the cases involved MCCBs not tripping within their specified tolerances. These MCCBs were evaluated by licensee engineering and determined to be capable of adequately tripping if required and capable of maintaining proper breaker coordination. One issue involved an MCCB that could not be reset following successful trip testing, and one involved an MCCB that had to have its testing sequence aborted when technicians identified some minor signs of smoke coming from the breaker. The MCCB that tripped but could not be reset was subsequently replaced by the licensee prior to Unit 1 restart. The MCCB that had its testing aborted was removed from service and sent to an offsite testing facility where its testing was completed within tolerances; the breaker was replaced, however, due to the minor signs of smoke noted by licensee technicians during its initial testing sequence.
Following their review, the inspectors queried the licensee regarding the number and nature of the testing issues observed, specifically asking about whether or not the scope and nature of the issues was comparable to prior refueling outage testing campaigns. The licensee entered the potential trend with A1R21 MCCB issues into their CAP as Issue Report (IR) 4305858. The licensees initial evaluation of their MCCB testing data from previous refuel outages did not indicate that this most recent MCCB testing campaign issues represented anything unusual.
The inspectors did not identify any findings or violations of NRC requirements in the course of their review.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 9, 2020, the inspectors presented the integrated inspection results to Ms. M Marchionda, Site Vice President and other members of the licensee staff.
- On October 11, 2019, the inspectors presented the radiation protection baseline inspection results to Ms. M. Marchionda, Site Vice President and other members of the licensee staff.
- On October 17, 2019, the inspectors presented the Inservice Inspection inspection results to Ms. M. Marchionda, Site Vice President and other members of the licensee staff.
- On November 20, 2019, the inspectors presented the URI 2018011-01 (FLEX) and EA 16-126 (Tornado Missile Discretion) Closures inspection results to Mr. R. Schliessmann, NRC Coordinator, and other members of the licensee staff.
- On December 5, 2019, the inspectors presented the Radiation Protection Inspection Results inspection results to Mr. J. Keenan, Plant Manager and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
4301787
NRC ID: Unit 1 Auxiliary Building Roof Drains Plugged
2/05/2019
Miscellaneous
Letter
20 Winter Readiness Certification
2/13/2019
Procedures
0BwOA ENV-1
Adverse Weather Conditions Unit 0
23
0BwOS XFT-A1
Unit Common Freezing Temperature Equipment Protection
Surveillance
0BwOS XFT-A2b
Unit Common Station Heat Area Heaters Freezing
Temperature Equipment Protection Surveillance
0BwOS XFT-A3
Unit Common Cold Weather Surveillance
0BwOS XFT-A4
Unit Common Freezing Temperature Equipment Protection
Inside Surveillance
0BwOS XFT-A5
Unit Common Freezing Temperature Equipment Protection
of Out Building Surveillance
General Area Checks and Operator Field Rounds
OP-AA-108-111-
1001
Severe Weather and Natural Disaster Guidelines
OP-BR-102-102-
1001
Augmented Operator Field Rounds
Seasonal Readiness
71111.04Q Drawings
ECCS-1
Training Document - Emergency Core Cooling System
Drawing
Procedures
Shutdown Reactor Coolant System (RCS) Makeup
BwOP AF-E1
Electrical Lineup - Unit 1 Operating
BwOP AF-M1
Operating Mechanical Lineup Unit 1
BwOP SX-E1
Electrical Lineup - Unit 1 Essential Service Water System
Operating
BwOP SX-E2
Electrical Lineup - Unit 2 Essential Service Water System
BwOP SX-M1
Operating Mechanical Lineup Unit 1
BwOP SX-M2
Operating Mechanical Lineup Unit 2
OP-BR-FX-1004
Medium Head FLEX Pump Operating Guideline
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.05Q Corrective Action
Documents
297714
Plant Barrier Impairment, BwAP 1110-1A4 Fire Watch
Communication Issue
11/15/2019
Fire Plans
No. 1; Fire Zone
1.1-1
Containment 377'-0" Elevation; Unit 1 Containment Missile
Shield Area
No. 2; Fire Zone
1.1-1
Containment 401'-0" Elevation; Unit 1 Containment Missile
Shield Area
No. 5; Fire Zone
1.2-1
Containment 377'-0" Elevation; Unit 1 Annular Area
No. 6; Fire Zone
1.2-1
Containment 401'-0" Elevation; Unit 1 Annular Area
No. 9; Fire Zone
1.3-1
Containment 426'-0" Elevation; Unit 1 Containment Upper
Area
Miscellaneous
Combustible
Permit 618
Reactor Head Stand Area
10/07/2019
Combustible
Permit 619
ROV Control Point for Head Lift
10/07/2019
Combustible
Permit 629
RCP Motor Replacement
01/07/2019
Combustible
Permit 630
Pipefitters Working RCP Motor
10/07/2019
Procedures
BwAP 1110-1
Fire Protection Program System Requirements
BwAP 1110-1A4
GOCAR [General Operation Condition Action Requirement]
Required Compensatory Measures Action Response Carbon
Dioxide Fire Suppression Systems
BwAP 1110-3
Plant Barrier Impairment Program
BwOP PBI-1
Plant Barrier Impairment Program Pre-Evaluated Barrier
Matrix
Plant Barrier Control Program
71111.05Q Procedures
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
Pre-Fire Plan Manual
Control of Transient Combustible Material
Corrective Action
Documents
202190
Unable to Complete Final Review for ASME XI Repair
Replacement
2/11/2018
286524
04-OSP-X A1R21 Snubber 1CV41036S Degraded Req's
Replacement
10/09/2019
287141
06-OSP-A A1R21 Snubber Operation Test Failure
1RC02006AS
10/11/2019
287143
06-OSP-A A1R21 Snubber Operation Test Failure
1RC02006BS
10/11/2019
287727
10-OSP-A (ISI) Constant Spring Can 1FW05024C FOUND
10/13/2019
287731
10-OSP-A (ISI) Variable Spring Can 1CV16034V FOUND
10/13/2019
287815
10-OSP-X Defer ASME Section XI Support Exam
1CC13045X (ISI)
10/14/2019
287816
10-OSP-X Defer ASME Section XI Support Exam on
1SX16019V (ISI)
10/14/2019
Miscellaneous
2410146-02
Eductor 1A Spray Add Suct Check VLV
06/22/2018
2731397-02
Bonnet Thermal Relief Valve for 1SI8811B
06/22/2018
NDE Reports
Reactor Head Surface Penetration 69
10/12/2019
10/13/2019
Main Steam Pipe to Elbow Weld 1-MS-02-24
10/17/2019
Main Steam Elbow to Pipe Weld 1-MS-02-25
10/17/2019
Main Steam Pipe to Elbow Weld 1-MS-02-26
10/17/2019
Main Steam Elbow to Pipe Weld 1-MS-02-32
10/17/2019
Main Steam Elbow to Pipe Weld 1-MS-02-29
10/17/2019
Main Steam Elbow to Pipe Weld 1-MS-02-27
10/17/2019
Main Steam Pipe to Elbow Weld 1-MS-02-28
10/17/2019
SN-19-0034
Pipe Support 1RC02006BS
10/10/2019
SN-19-0041
Pipe Support 1RC02006AS
10/10/2019
Procedures
Liquid Penetrant (PT) Examination
ER-AA-335-015-
2013
VT-2 Visual Examination in Accordance with ASME 2013
Visual Examination of ASME IWE Class MC and Metallic
Liners of IWL Class CC Components
Ultrasonic Examination of Austenitic Piping Welds
Ultrasonic Examination of Studs and Bolts
Code Acceptance & Recording Criteria for Nondestructive
(NDE) Surface Examination
Bare Metal Visual Examination for Nickel Alloy Materials
EXE-PDI-UT-2
Ultrasonic Examination of Austenitic Pipe Welds in
Accordance with PDI-UT-2
EXE-PDI-UT-5
Straight Beam Ultrasonic Examination of Bolts and Studs in
Accordance with PDI-UT-5
Work Orders
04775229-01
1CV8396B Is Spraying from Diaphragm Between Body and
04/20/2018
71111.11Q Procedures
1BwGP 100-4
Power Decension
OP-AA-101-111-
1001
Operations Standards and Expectations
Operator Fundamentals
OP-AA-101-113-
1006
4.0 Crew Critique Guidelines
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
Corrective Action
Documents
4149917
Oil Slinger Ring Not Installed on 0A and 0B VC Chillers
06/24/2018
297028
Degradation on 0B VC Chiller Condenser Head Flange
Faces
11/13/2019
297481
Rejectable NDE Indication 0WO01CB Outlet Flange
11/15/2019
Procedures
Maintenance Rule Functions - Safety Significant
Classification
Maintenance Rule Implementation per NEI 18-10
Maintenance Rule 18-10 - Scoping
Maintenance Rule 18-10 - Failure Definitions
Maintenance Rule 18-10 - Performance Monitoring and
Dispositioning Between (a)(1) and (a)(2)
Work Orders
1917679
Replace 0TS-WO207 - Chiller 0WO1CB Hot Gas Bypass
Temperature Switch
11/24/2019
29795
0WO01CB: Replace Guide Vanes
11/13/2019
4609716
0WO01CB Condenser PM and Eddy Current Testing
11/12/2019
4802125
Oil Slinger Ring Not Installed on 0A and 0B VC Chillers -
Disassemble / Take Measurements / Reassemble Chiller
11/14/2019
Corrective Action
Documents
287867
09-OSP-A: 1C Steam Generator PORV Hydraulic Reservoir
Level Low
10/15/2019
288936
13-OSP-A: Annunciator 1-15-C10, Steam Generator 1C
PORV Trouble
10/18/2019
293122
1-/15-C10, Steam Generator 1C PORV Trouble - 1MS018C
Hydraulic Fluid Low
10/31/2019
297820
1-15-A10: Steam Generator 1A PORV Trouble - Accumulator
Pressure Low
11/16/2016
Corrective Action
Documents
Resulting from
Inspection
295505
1MS018C Lost Paperwork for Hydraulic Fill Evolution
11/07/2019
Procedures
1BwOSR
3.6.3.5.MS-1
Main Steam System Containment Isolation Valve Stroke
Surveillance
Risk Management
ER_AA-600-1042
On-Line Risk Management
Conduct of Troubleshooting
Protected Equipment Program
On-Line Risk Management and Assessment
Work Orders
4970682
1MS018C Add Oil to PORV (Unscheduled Maintenance)
11/08/2019
Corrective Action
Documents
2673854
Non-Conforming Conditions Identified - Tornado Missiles
05/25/2016
4014784
1Q17 LIV - Lack of Adequate Tornado Missile Protection
05/25/2017
4109224
NRC URI - Tornado Missile Protection for Installed
Equipment
2/28/2018
285855
2-OSP: 1A Auxiliary Feedwater Pump Breaker did not
Close During ATWS (Anticipated Transient Without Scram)
Testing
10/08/2019
298842
2B DG EMG Stop Due to Abnormal JW Surging
11/20/2019
Drawings
M-152, Sheet 14
Manufacturers Supplemental Diagram of Diesel Generator
Jacket Water Schematic Units 1 & 2
V
Procedures
1BwOS ATWS-
R1
Unit 1 Anticipated Transient Without Scram Mitigation
System Refueling Outage End to End Surveillance
2BwOSR 3.8.1.2-
Unit 2B Diesel Generator Operability Surveillance
BwOP AF-5
Motor-Driven Auxiliary Feedwater Pump 'A' Startup on
Recirculation
BwOP DG-11
Diesel Generator Startup and Operation
BwOP DG-11T2
Diesel Generator Operating Log
Risk Management Documentation
OP-AA-106-101-
1006
Operational Decision Making Process
Adverse Condition Monitoring and Contingency Planning
Operability Determinations (CM-1)
Work Orders
1956941
Unit 1 ATWS (Anticipated Transient Without Scram)
Refueling Outage Testing
04/09/2018
1956941
Unit 1 ATWS [Anticipated Transient Without Scram]
Refueling Outage Testing
04/09/2018
Corrective Action
Documents
272924
EC 627959 Follow-Up Actions for Auxiliary Feedwater
Procedure Changes
08/19/2019
280595
CDO - Inadequate 50.59 Review for EC 625405
09/12/2019
Engineering
Changes
25405
Unit 1 Ovation Post N-Outage Backfit
27959
Auxiliary Feedwater System Operation to Support a Loss of
Normal Feedwater During a Unit Startup
Procedures
EC 625405-1
Braidwood Station N+1 Outage Mod Acceptance Test (MAT)
Corrective Action
Documents
299555
0WO01CB Chiller Tripped
11/24/2019
Operability
Evaluations
BwVP 500-14
Core Alignment Verification
Procedures
1BwOS RD-3
Shutdown Rod Insertion Limit During Approach to Criticality
Surveillance
1BwOS TRM
3.1.k.1
Unit 1 Digital Rod Position Indication (DRPI) Operability
Verification Prior to and During Rod Drop Testing
1BwOSR 3.1.7.1
Digital Rod Position Indication (DRPI) Operability Checkout
1BwOSR
3.8.1.19-2
1B Diesel Generator ECCS Sequencer Surveillance
1BwOSR 3.8.11-
1B Diesel Generator Loss of ESF Bus Voltage with No SI
Signal
1BwOSR
5.5.8.CV-4A
Group A IST Requirements for 1A Centrifugal Charging
Pump (1CV01PA) and Check Valve 1CV8480A Stroke Test
BwISR 3.1.4.3.a
Rod Drop Time (Automatic)
Core Verification Guideline
Newton Core Gap Alignment Data Acquisition for Byron and
Braidwood
Work Orders
1966510
1B Diesel Generator 24 Hour Load Test and ECCS
Surveillance
10/26/2019
4709143
Functional Run of 0WO01CB Following Control Panel Relay
Replacements
11/24/2019
4751413
1CV01PA Disassemble, Inspect & Clean Gearbox Oil Filter
10/16/2019
4751462
Check Shaft Driven Oil Pump Drive Mechanism
10/16/2019
475147B
1B Diesel Generator Loss of ESF Buss Voltage with No SI
Signal
10/16/2019
4775529
Core Alignment Verification - Unit 1
10/16/2019
4781082
Unit 1 Digital Rod Position Indication (DRPI) Operability
Checkout
10/21/2019
4790778
Change Oil in Motor Bearings and Take Sample
10/16/2019
4798246
Perform 2 Year Inspection of Diesel Generator
2/15/2019
20752
Unit 1 Automatic Rod Drop Time Surveillance
10/21/2019
4875703
1SC-DG250B Replace DG Governor Actuator
2/15/2019
4897408
Digital Rod Position Indication (DRPI) Surveillance During
Rod Drop Testing
10/21/2019
Corrective Action
Documents
286018
2 DC Ground
10/08/2019
286592
Unexpected Toggling of Alarm SR S/D Flux High
10/10/2019
289506
Mode 3 Entry with LCO 3.0.4B Requirements
10/20/2019
289892
Active Water Leak in Unit 1 Seal Table Room
(Clean/Tighten)
10/21/2019
Corrective Action
Documents
Resulting from
Inspection
285795
NRC ID: BWOP RC-4 Improvement Opportunity
10/07/2019
Procedures
1BwGP 100-1
Plant Heatup
1BwGP 100-3
Power Ascension 5% to 100%
1BwGP 100-5
Plant Shutdown and Cooldown
1BwOS TRM
2.5.b.1
Unit 1 - Containment Loose Debris Inspection
BwAP 1450-1
Access to Containment
BwGP 100-2
Plant Startup
BwOP DG-1
Diesel Generator Alignment to Standby Condition
BwOP RC-4
Reactor Coolant System Drain
BwVS 500-6
Low Power Physics Test Program
BwVS TRM
3.1.h.1
Core Reload Sequence and Verification
Pre-Job Briefings
Fatigue Management and Work Hour Rules
Reactor Services: Refuel Floor FME Plan
Unit Restart Review
Evaluation of Special Tests or Evolutions
Corrective Action
Documents
1BwOSR
5.5.8.AF-4A
Unit One Comprehensive Inservice Testing (IST)
Requirements for 1A Auxiliary Feedwater Pump
284962
1MS015A Did Not Pass As Found Testing
10/04/2019
286889
06-OSP-X: Safety Injection Full Flow Testing Post
Calibration Unsatisfactor
10/10/2019
Procedures
1BwOSR 3.3.2.9-
Unit One - Train B Safety Injection Manual Initiation and
Phase "A" Containment Isolation Manual Initiation
Surveillance
1BwOSR 3.6.1.1-
Primary Containment Type C Local Leakage Rate Test of
Make-Up Demineralizer System
1BwVSR 3.6.1.25
Summation of Type "B" & "C" Tests for Acceptance Criteria
2BwOSR
3.8.1.13-1
2A Diesel Generator Bypass of Automatic Trips Surveillance
2BwOSR 3.8.1.2-
2A Diesel Generator Operability Surveillance
BwMP 3305-003
Main Steam Safety Valve Testing Using Setpoint Verification
Device
BwOP DG-11
Diesel Generator Startup and Operation
BwOP GD-12
Diesel Generator Shutdown
Work Orders
1961853
IST - Unit 1 Local Leak Rate Test WM 190/191 for
Containment Penetration No. 30
10/18/2019
1966521
Unit 1 Train B SI Signam Manual Initiation and Phase A
Containment Isolation Manual Initiation
10/07/2019
4787030
2DG01KA Bypass of Automatic Trips Not with Slave Start
11/06/2019
4795683
IST-Unit 1 AF Pumps Comprehensive Full Flow Test and
Equipment Response Time
10/05/2019
21955
Unit 1 Local Leak Rate Test Summation for Type "B" & "C"
Tests
10/20/2019
4851024
IST - Main Steam Safety Valve Test for
1MS013S/014S/015S/016S/017S
10/03/2019
4971355
2A Emergency Diesel Generator Monthly
11/06/2019
Procedures
Standardized Radiological Emergency Plan
Radiological Emergency Plan Annex for Braidwood Station
Monthly Data Elements for NRC Reactor Coolant System
(RCS) Leakage
Calculations
BW-01-19-00513
Airborne Radioactivity Calculation Worksheet; U-1 426'
Inside Cavity
10/09/2019
BW-01-19-00619
Airborne Radioactivity Calculation Worksheet U-1 377' In-
Core Sump
10/07/2019
BW-01-19-00641
Airborne Radioactivity Calculation Worksheet U-1
Containment 426' Reactor Head
10/11/2019
BW-01-19-00649
Airborne Radioactivity Calculation Worksheet U-1 401' Seal
Table
10/08/2019
Procedures
Controls for High and Locked High Radiation Areas
Radiation
Surveys
054691
Containment 426' Lower Cavity
10/07/2019
054692
Containment 401' Inside Missile Barrier
10/07/2019
054699
Containment 426' Upper Cavity
10/07/2019
054705
Containment 377 Outside Missile Barrier
10/07/2019
958270
Containment 390' A&D Steam Generator Platform
10/07/2019
958270
Containment 390' Steam Generator B&C Platform
10/07/2019
Radiation Work
Permits (RWPs)
BW-01-19-00615
Reactor Cavity Work
ALARA Plans
BW-01-19-00613
Reactor Head Disassembly/Reassembly
BW-01-19-00614
Reactor Head and Upper Internal Move
BW-01-19-00619
Under-vessel Activities
BW-01-19-00649
Seal Table Room Outage Activity
Miscellaneous
Sample ID
0VA05FA
Radioiodine Test Report
07/06/2018
Sample ID
0VA05FB
Radioiodine Test Report
07/06/2018
Sample ID
0VA05FC
Radioiodine Test Report
07/06/2018
Sample ID
0VA05FD
Radioiodine Test Report
06/15/2018
Sample ID
0VA05FE
Radioiodine Test Report
06/15/2018
Sample ID
0VA05FF
Radioiodine Test Report
06/15/2018
Work Orders
01937904 01
Auxiliary Building Vent Stack Wide Range Gas Monitor Full
Calibration
05/11/2018
Corrective Action
Documents
Spent Resin Pump 0WX79MA Does Not Rotate
06/18/2018
Brine Tank Booster Pump Degraded
11/09/2018
0WX05DB Radwaste Demin is Leaking
03/13/2019
Resin Not Available For The 1CV01DA De-Boration Bed
Sluice
09/09/2019
Corrective Action
Documents
Resulting from
Inspection
NRC Open Item From Inspection Regarding RW Resin Resin
Sampling
10/20/2017
Engineering
Changes
0000623825
TCCP To Restore 0WX889-XA Interlocks to Allow Water
Processing Through 0W889 and 0WX890
04/10/2018
Miscellaneous
CFR 61 Primary Filter Waste Stream Analysis
01/14/2019
CFR 61 Radwaste Resin Analysis
2/03/2018
CFR 61 Dry Activated Waste (DAW) Analysis
01/29/2019
Procedures
Process Control Program for Radioactive Wastes
Self-Assessments AR 04214019
NRC Inspection IP 71142.08 Radioactive Solid Waste
Processing and Radioactive Material Handling, Storage and
Transportation
07/11/2019
Shipping Records RWS19-003
0WX05T Resin Liner PO676656-19 in Cask RT-100 #3
03/05/2019
RWS19-004
0WX05T Resin in Liner PO676656-13 in Cask RT-100 #3
03/12/2019
RWS19-012
B-25s of Grossly Dewatered Resin
07/18/2019
RWS19-014
Resin Liner PO683742-17 in Cask
09/25/2019
71151
Miscellaneous
Monthly Data Element for NRC Reactor Coolant System
Specific Activity
03/2018 -
06/2019
Monthly Data Elements for NRC RETS/ODCM Radiological
Effluent Occurrences
07/2018 -
07/2019
NRC
Performance
Indicator Data
Barrier Integrity - RCS Identified Leakage
10/01/2018 -
09/30/2019
Procedures
Collecting and Reporting of NRC Performance Indicator Data 15
Corrective Action
Documents
0699328
1FW079B Check Valve Further Closed Than Expected
11/14/2007
4141563
Ovation Alarm Associated with 1FW520
05/26/2018
4165777
1FW079B Check Valve Further Closed Than 1FW079A, C,
and D
08/20/2019
287309
08-OSP-A A1R21 ODEN 1AP27E-D1 Fail to Reset
(1VX01C) Test
10/12/2019
287313
A1R21 ODEN 1AP27E-C4F (1RY8000B) Tripped Out of
Tolerance Low
10/12/2019
287314
A1R21 ODEN 1AP23E-G4F (OSX165B) Tripped Out of
Tolerance
10/12/2019
287316
ODEN 1AP23E-G4R (0SX165B) Tripped Out of Tolerance
10/12/2019
287396
09-OSP-A A1R21 ODEN 1AP28E-D4 Did Not Trip
10/13/2019
287492
08-OSP-R A1R21 ODEN 1AP32E-D5 (1OG084) Tripped Out
of Tolerance
10/13/2019
291137
1FW1137 Full Open Following Power Ascension
10/25/2019
291137
1FW530 Full Open Following Power Ascension
10/25/2019
298999
Trend IR - Breaker Deficiencies in Breaker Refurbishments
11/21/2019
4305858
Trend IR for A1R21 ODEN Testing
2/23/2019
Procedures
Quality Assurance Topical Report (QATR)
Issue Identification and Screening Process
Corrective Action Program (CAP) Procedure
Root Cause Analysis Manual
Corrective Action Program Evaluation Manual
Corrective Action
Documents
287444
11-OSP-A: Preliminary Data - Manufacturing Defect on
1FW520 Digital Valve Controller Relay
10/13/2019
292282
Inadvertent Siren Activation of Will County Sirens
10/29/2019