IR 05000456/2019003
| ML19312A525 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  (NPF-072, NPF-077) |
| Issue date: | 11/08/2019 |
| From: | Hironori Peterson Region 3 Branch 3 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| References | |
| EA-19-116 IR 2019003 | |
| Download: ML19312A525 (31) | |
Text
November 8, 2019
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000456/2019003 AND 05000457/2019003
Dear Mr. Hanson:
On September 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Braidwood Station, Units 1 and 2. On October 17, 2019, the NRC inspectors discussed the results of this inspection with the Plant Manager, Mr. J. Keenan, and other members of your staff. The results of this inspection are documented in the enclosed report.
One Severity Level IV violation without an associated finding 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.
If you contest the violation or significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; the Director, Office of Enforcement; and the NRC Resident Inspector at Braidwood. 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
Inspection Report
Docket Numbers:
05000456 and 05000457
License Numbers:
Report Numbers:
05000456/2019003 and 05000457/2019003
Enterprise Identifier: I-2019-003-0059
Licensee:
Exelon Generation Company, LLC
Facility:
Braidwood Station, Units 1 and 2
Location:
Braceville, IL
Inspection Dates:
July 01, 2019 to September 30, 2019
Inspectors:
R. Baker, Senior Operations Engineer
B. Bergeon, Operations Engineer
R. Bowen, Illinois Emergency Management Agency
D. Kimble, Senior Resident Inspector
C. Phillips, Project Engineer
M. Porfirio, Illinois Emergency Management Agency
L. Rodriguez, Reactor Inspector
R. Ruiz, Project Engineer
P. Smagacz, Resident Inspector
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.
List of Findings and Violations
Failure of the facility licensee to certify that a licensed senior operator with an inactive license completed the requirements of 10 CFR 55.53(f) before resuming functions authorized by a license.
Cornerstone Significance Cross-Cutting Aspect Report Section Not Applicable NCV 05000456,05000457/2019003-01 Open/Closed EA-19-116 Not Applicable 71111.11B The inspectors identified a Severity Level IV non-cited violation (NCV) of 10 CFR 55.53(f) for the failure of the facility to certify that a senior licensed operator with an inactive license completed the requirements to return the license to an active status before resuming functions authorized by the license. Specifically, a senior reactor operator whose license was no longer in an active status was permitted to relieve the unit supervisor watch. As this individual was no longer permitted to perform the functions of a senior operator, and subsequently was the only senior reactor operator in the control room for a period of time during the shift, the facility did not ensure a senior operator with an active license was present in the control room at all times when both units were in Mode 1.
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period operating at full power. On July 23, 2019, power was reduced to approximately 30 percent to facilitate electrical repairs to a solenoid valve associated with the 1D Steam Generator (SG) Feedwater Regulating Valve (1FW540). Upon completion of the repair activities and associated post-maintenance testing, the unit returned to operation at full power on July 25, 2019. On September 18, 2019, the unit reached the end of the nuclear fuel cycle and entered planned power coast down operations in preparation for its 21st refueling outage. Late in the morning on September 23, 2019, the unit tripped while operating at approximately full power when the 1B SG Feedwater Regulating Valve (1FW520) unexpectedly failed to the closed position. Following the identification of failed digital control components associated with the 1FW520 valve, the unit was restarted and the reactor made critical on September 24, 2019. Synchronization of the main electrical generator to the power grid occurred later that same morning. The unit had reached approximately 90 percent power at the end of the inspection period with power coast down operations continuing.
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 balance of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed 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
71111.04Q - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system conditions and configuration by conducting partial physical alignment verifications of the following systems/trains:
- (1) The 1A Residual Heat Removal (RH) train with the 1B RH out of service for planned maintenance during the week ending July 27, 2019
- (2) The 1B Safety Injection (SI) train with the 1A SI train out of service for planned maintenance during the week ending August 3, 2019
- (3) The 1A SI train with the 1B SI train out of service for planned maintenance during the week ending August 24, 2019
- (4) The 2A SI train with the 2B SI train out of service for planned maintenance during the week ending September 21, 2019
71111.04S - Equipment Alignment
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the configuration and condition of the Unit 2 SI system during a full system physical alignment verification during the weeks ending September 7 through September 14, 2019
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (8 Samples)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) The Division 11 Engineered Safety Feature (ESF) Switchgear Room, Fire Zone 5.2-1, during the weeks ending July 13 through July 20, 2019
- (2) The Unit 1, Non-ESF Switchgear Room, Fire Zone 5.3-1, during the weeks ending July 13 through July 20, 2019
- (3) The Division 12 ESF Switchgear Room, Fire Zone 5.1-1, during the weeks ending July 13 through July 20, 2019
- (4) The Division 21 ESF Switchgear Room, Fire Zone 5.2-2, during the weeks ending July 13 through July 20, 2019
- (5) The Division 22 ESF Switchgear Room, Fire Zone 5.1-2, during the weeks ending July 13 through July 20, 2019
- (6) Unit 2 Non-ESF Switchgear Room, Fire Zone 5.3-2, during the weeks ending July 13 through July 20, 2019
- (7) The Division 12 Miscellaneous Electrical Equipment Room and Battery Room, Fire Zone 5.4-1, during the weeks ending July 13 through July 20, 2019
- (8) The Division 22 Miscellaneous Electrical Equipment Room and Battery Room, Fire Zone 5.4-2, during the weeks ending July 13 through July 20, 2019
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 02.02a.) (1 Sample)
The inspectors evaluated internal flooding vulnerability and mitigation for the following plant area:
- (1) The Unit 1 Auxiliary Feedwater (AF) area, 383' Elevation, during the week ending September 28, 2019
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered from August 19, 2019 through September 20, 2019.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)
- (1) Biennial Requalification Written Examinations
The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered on August 17, 2018.
Annual Requalification Operating Tests
The inspectors evaluated the adequacy of the facility licensees annual requalification operating test.
Administration of an Annual Requalification Operating Test
The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.
Requalification Examination Security
The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.
Remedial Training and Re-examinations
The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions
The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.
Control Room Simulator
The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
Problem Identification and Resolution
The inspectors evaluated the licensees ability to identify and resolve problems associated with licensed operator performance.
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)
The inspectors observed and evaluated licensed operator performance in the station's Main Control Room during the following activities:
- (1) Various periods of high-tempo and/or risk-significant operations during the weeks ending July 27 through September 28, 2019
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (2 Samples)
The inspectors observed crews of licensed operators in the station's simulator during the following evaluated and graded casualty training scenarios:
- (1) An evaluated and graded casualty scenario on July 9, 2019
- (2) An evaluated and graded casualty scenario on September 18, 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 issues:
- (1) The 2B Main Feedwater (FW) Pump lube oil system and performance issues as documented in Issue Report (IR) 426503 during the weeks ending August 3 through August 10, 2019
- (2) The Unit 1 Main Control Room annunciator system and performance issues as documented in IR 4264965 during the weeks ending August 10 through August 31, 2019
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's risk assessments and planning for the following work activities:
- (1) Emergent repairs to 125 volts direct current (Vdc) Bus 111 grounds as documented in Work Order (WO) 4920701 during the week ending July 27, 2019
- (2) Emergent work to repair a Unit 1 annunciator logic error as documented in IR 4264965 during the weeks ending July 27 through August 3, 2019
- (3) Troubleshooting and repairs to the 2B Main FW Pump lube oil system as documented in WO 4850789 during the week ending August 10, 2019
- (4) Emergent repairs to the 1B Steam Generator Main Feedwater Regulating Valve (1FW520) as documented in WO 4962887 during the week ending September 28, 2019
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 02.02) (8 Samples)
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) The evaluation of a noisy and slowly increasing demand signal associated with the 1D Steam Generator FW Regulating Valve (1FW540) controller as documented in IR 4259918 during the week ending July 20, 2019
- (2) The evaluation of an American Society of Mechanical Engineers Code nonconformance for Unit 1 replacement steam generators as documented in IR 4272501 during the weeks ending August 24 through August 31, 2019
- (3) The evaluation of the functionality of the 2B Main FW Pump after foreign material was introduced into the pump's oil system as documented in IR 4270893 during the weeks ending August 17 through September 14, 2019
- (4) The evaluation of the operability of direct current (DC) distribution panels following the identification of duct tape being used to secure spare fuse holders in the DC distribution panels as documented in IR 4273062 during the weeks ending August 24 through September 7, 2019
- (5) The evaluation of the 1A Essential Service Water (SX) Pump strainer backwashing excessively as documented in IR 4274831 during the weeks ending August 31 through September 7, 2019
- (6) The evaluation of Air Circuit Breaker (ACB) 1424 requiring multiple attempts to close during the Bus 142/242 cross-tie surveillance as documented in IR 4276343 during the weeks ending September 7 through September 14, 2019
- (7) The evaluation of DC Bus 112 battery cell 2 low specific gravity as documented in IR 4272834 during the weeks ending September 7 through September 14, 2017
- (8) The evaluation of the 2B AF Pump with a degraded engine fan coupling as documented in IR 4279078 during the week ending September 21, 2019
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following permanent modification to the facility:
- (1) Permanent enhancements and upgrades to the cooling systems for the Unit 1 and Unit 2 Miscellaneous Electrical Equipment Rooms as documented in Engineering Changes (ECs) 624901 and 624903 during the weeks ending August 17 through September 14, 2019
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the following post maintenance testing activities and results:
- (1) Electrical acceptance testing following repairs to 125 Vdc Bus 111 as documented in WO 4920701 during the week ending July 27, 2019
- (2) Functional testing of the 1B RH Pump following planned maintenance as documented in WO 4917400 during the weeks ending July 27 through August 10, 2019
- (3) Functional and operational testing of the 2A EDG following planned maintenance as documented in WOs 4943770, 4921630, and 4758895 during the week ending August 10, 2019
- (4) Functional and operational testing of the 0B Diesel-Driven Fire Pump following replacement of the pump element as documented in WOs 04843529 and 04947232 during the weeks ending August 3 through August 17, 2019
- (5) Functional and operational testing of the 2B Containment Spray (CS) Pump following planned maintenance as documented in WOs 4925636, 4654936, and 4671383 during the week ending August 17, 2019
- (6) Functional and operational testing of the 1B SI Pump following planned maintenance as documented in WOs 1764793, 1843557, 1898770, 1914717, 4613459, and
===4680012 during the week ending August 24, 2019
- (7) Functional and operational testing of the DC Bus 111 Battery Charger (1DC03E)following emergent repairs as documented in WO 46667971 during the week ending September 14, 2019
71111.22 - Surveillance Testing
.Surveillance Tests (other) (IP Section 03.01)===
The inspectors observed and evaluated the following licensee surveillance testing activities:
(1)2BwOSR 3.8.1.2-1, 2A Diesel Generator Operability Surveillance as documented in WO 4933550 during the week ending July 12, 2019 (2)0BwOS CW-1, U0 Circulating Water (CW) Blowdown Vacuum Breaker inspection as documented in WO 4943151 during the week ending August 10, 2019 (3)1BwOSR 3.7.5.4-2, 1B AF monthly surveillance as documented in WO 4943151 during the weeks ending August 17 through August 24, 2019 (4)2BwOSR 3.8.1.8-1, Station Auxiliary Transformer (SAT) 142-1 crosstie to Bus 241 18-Month Surveillance as documented in WO 4724064 during the week ending September 7, 2019
FLEX Testing (IP Section 03.02) (1 Sample)
The inspectors observed and evaluated the following licensee FLEX Testing activities:
===4674064 during the weeks ending August 31 through September 7, 2019
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03)===
The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes:
- (1) Evaluation 18-45; Exelon Nuclear Standardized Radiological Emergency Plan, Revision 30; 02/14/2019
This evaluation does not constitute NRC approval.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicator information by reviewing selected information for the periods listed below:
MS08: Heat Removal Systems (IP Section 02.07)===
- (1) Unit 1 (July 1, 2018, through June 30, 2019)
- (2) Unit 2 (July 1, 2018, through June 30, 2019)
MS09: Residual Heat Removal Systems (IP Section 02.08) (2 Samples)
- (1) Unit 1 (July 1, 2018, through June 30, 2019)
- (2) Unit 2 (July 1, 2018, through June 30, 2019)
MS10: Cooling Water Support Systems (IP Section 02.09) (2 Samples)
- (1) Unit 1 (July 1, 2018, through June 30, 2019)
- (2) Unit 2 (July 1, 2018, through June 30, 2019)
71152 - Problem Identification and Resolution
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)
The inspectors reviewed the licensees implementation of their corrective action program (CAP) related to the following issues:
- (1) Review of corrective actions for the 1D Steam Generator Main FW Regulating Valve (1FW540) DC grounds as documented in IRs 4209878, 4248185, and 4265545 during the weeks ending August 3, 2019, through September 28, 2019
===71153 - Follow-up of Events and Notices of Enforcement Discretion
The inspectors reviewed the licensee's response to the following event:
Event Follow-up (IP Section 03.01)===
- (1) Response to the Unit 1 automatic reactor trip on September 23, 2019, due to a 1B Steam Generator Lo-Lo Level condition as documented in NRC Event Notification (EN)
INSPECTION RESULTS
Failure of the facility licensee to certify that a licensed senior operator with an inactive license completed the requirements of 10 CFR 55.53(f) before resuming functions authorized by a license.
Cornerstone Severity Cross-Cutting Aspect Report Section Not Applicable Severity Level IV NCV 05000456,05000457/2019003-01 Open/Closed EA-19-116 Not Applicable 71111.11B The inspectors identified a Severity Level IV non-cited violation (NCV) of 10 CFR 55.53(f) for the failure of the facility to certify that a senior licensed operator with an inactive license completed the requirements to return the license to an active status before resuming functions authorized by the license. Specifically, a senior reactor operator whose license was no longer in an active status was permitted to relieve the unit supervisor watch. As this individual was no longer permitted to perform the functions of a senior operator, and subsequently was the only senior reactor operator in the control room for a period of time during the shift, the facility did not ensure a senior operator with an active license was present in the control room at all times when both units were in Mode 1.
Description:
On August 20, 2019, the NRC identified a licensed senior operator who had been performing the functions of a senior operator with an inactive license. The licensed senior operator had been off-shift, in another department, for a few years and was not maintaining his license in an active status. The senior operator restored the active status of his license by completing 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of shift functions under the direction of a proficient senior operator as of December 20, 2018 (4th quarter 2018), in accordance with 10 CFR 55.53(f)(2). The senior operator's reactivation record was not reviewed and approved until January 4, 2019. Subsequently, the senior operator was incorrectly entered into the facility's qualification system as having completed the requirements to return the license to an active status in the 1st quarter 2019.
As a result, the senior operator did not stand all of the required seven 8-hour or five 12-hour shifts in the 1st quarter 2019 and the license once again reverted to an inactive status as of April 1, 2019. The senior operator was then permitted to stand 12 watches during the 2nd and 3rd quarters of 2019, without a license in active status. This was the result of the facility licensee's failure to certify that a licensed senior operator with an inactive license completed the requirements of 10 CFR 55.53(f) before resuming functions authorized by the license.
Additionally, these actions resulted in the facility licensee not meeting the requirements of 10 CFR 50.54(m)(2)(iii) and Technical Specification 5.1.2, to have a person with a senior operator license, capable of performing the functions of that position, in the control room at all times and having a senior reactor operator responsible for the control room command function when either unit is in Mode 1, 2, 3, or 4, respectively. Since these 2 violations were the direct result of the violation of the licensed operator's license condition, they will be dispositioned as part of the Severity Level IV violation.
Corrective Actions: The facility immediately removed the licensed operator from the qualification tracking system and placed the individual on administrative hold from performing licensed duties. The facility also conducted a stand down with all Operations crews, the Operations Training department personnel, and the Department Training Coordinators on the issue, as well as performing an extent of condition review of all recently reactivated licenses in 2018 and 2019. No additional issues were identified with SROs or ROs standing shifts with an inactive license. An operation's Standing Order was issued for each licensed operator to verify qualifications and license restrictions for watch standing every shift prior to watch standing and audited by the Senior Operations Supervisor.
Corrective Action References: IR 04273460; OP-AA-105-102, Attachment 1 not complete for 1st quarter 2019; dated 8/21/2019. IR 04274629; EOC [Extent of Condition] of Operator License Maintenance Review; dated 8/27/2019.
Performance Assessment:
The inspectors determined that the facility incorrectly credited a senior operator's license reactivation in the calendar quarter following the quarter in which the under-direction watches were completed, and then subsequently permitted the senior operator to stand watch in the control room with an inactive license. This error constituted a performance deficiency that was within the facility's ability to foresee and correct and should have been prevented. The inspectors determined that Traditional Enforcement applied, as the issue had the potential to impact the NRC's ability to perform its regulatory function. The NRC may need to perform a review in consideration of a licensing action, if a licensed operator fails to meet the conditions of their license. If the information regarding the qualifications of an individual is not accurately presented, the NRC may potentially make an incorrect licensing decision based on the inaccurate information. Specifically, the facility did not certify that a licensed senior operator, whose license became inactive at the end of 1st quarter 2019, completed the requirements of 10 CFR 55.53(f) before resuming functions authorized by the license, and permitted the senior operator to stand watches in the 2nd and 3rd quarters of 2019. These actions violated a license condition as specified in 10 CFR 55.53
- (e) and (f). No associated Reactor Oversight Program finding was identified, and no cross-cutting aspect was assigned.
Enforcement:
The ROPs significance determination process does not specifically consider the regulatory process impact in its assessment of licensee performance. Therefore, it is necessary to address this violation which impedes the NRCs ability to regulate using traditional enforcement to adequately deter non-compliance.
Severity: This issue is similar to the violation example 6.4.c.1(c) in the NRC Enforcement Policy, dated May 28, 2019, for a Severity Level III violation because it involved the noncompliance with a condition stated on an individuals license. However, since the amount of time that lapsed between consecutive watches was never more than a calendar quarter, and the length of time used to complete 5 consecutive watches was within the intent of the requirement, along with the fact that there were no adverse impacts to nuclear safety, the NRC has determined that this issue will be dispositioned as a Severity Level IV NCV in accordance with the NRCs Enforcement Policy.
Violation: Title 10, of the Code of Federal Regulations (CFR), 55.53(e) requires, in part, that if a licensee has not been actively performing the functions of an operator or senior operator, the licensee may not resume activities authorized by a license issued under this part except as permitted by paragraph
- (f) of this section. Section 55.53(f) states, If paragraph
- (e) of this section is not met, before resumption of functions authorized by a license issued under this part, an authorized representative of the facility licensee shall certify the following:
- (1) That the qualifications and status of the licensee are current and valid; and
- (2) That the licensee has completed a minimum of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of shift functions under the direction of an operator or senior operator as appropriate and in the position to which the individual will be assigned. The 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> must have included a complete tour of the plant and all required shift turnover procedures.
Title 10 CFR 50.54(m)(2)(iii) requires, in part, that when a nuclear power unit is in an operational mode other than cold shutdown or refueling, as defined by the units technical specifications, each licensee shall have a person holding a senior operator license for the nuclear power unit in the control room at all times.
The facility Technical Specification (TS) Section 5.1.2, states, in part, that a senior reactor operator shall be responsible for the control room command function while either unit is in Mode 1, 2, 3, or 4.
Contrary to the above, between April 1, 2019 and August 6, 2019, the facility licensee failed to certify that a licensed senior operator with an inactive license completed the requirements of 10 CFR Part 55.53(f) before resuming functions authorized by a license issued by the NRC.
Additionally, on June 18, 2019, for several periods totaling approximately 16 minutes and 47 seconds, there was not a Senior Reactor Operator in the control room with an active license. Therefore, the facility licensee failed to meet the requirements of 10 CFR 50.54(m)and TS 5.1.2 for minimum control room staffing. Because these violations were the result of the facility licensees failure to meet the requirements of 10 CFR Part 55.53(f) to certify that the senior reactor operator who was on shift had an active license, these violations will be dispositioned as part of the Severity Level IV violation.
Enforcement Action: This violation is being treated as an non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Observation: Steam Generator (SG) 1D Main Feedwater Regulating Valve (FRV) 1FW540, DC Bus Grounds 71152 The inspectors performed detailed reviews of IR 4209878, DC Bus 111 Ground Coming in with 1PL01J Panel Check, IR 4248185, DC Bus 111 Ground, and IR 4265545, Unexpected Annunciator 1-21-D6: DC Bus 111 Ground. The licensees evaluation for this issue went back to the previous Unit 1 refueling outage (A1R20) that took place during April of 2018.
During that refuel outage, digital FRV positioners were installed on all applicable valves on Unit 1. As part of this upgrade, new solenoid valves were also installed on the associated FRV actuators. Licensee troubleshooting identified that a solid DC Bus 111 ground was located between terminal box 1JB080T and the A solenoid valve, 1FSV-FW540-A, on FRV 1FW540. Upon inspection, one of the lugs/screws for the solenoid wiring terminations was excessively long, significantly longer than the others used for the project, and eventually wore through the insulating tape that had been applied causing the electrical connection to short out against the conduit body.
The cause of the ground was determined by the licensee to have been poor worker craftsmanship. Contractor electricians performing the solenoid replacement for 1FSV-FW540-A did not use the hardware referenced in the work package material request as specified. The lug/screw for the solenoid wiring termination that was significantly longer than the others required a different taping/insulating technique, which was not utilized.
Furthermore, the taping/insulating procedure referenced in the work package was for the use of the hardware specified within the material request. The licensees investigation could not determine why one lug/screw utilized in making up the connection was significantly longer than the others. New hardware of a shorter dimension had been requested and associated with the work package, and was on site and available for use.
Although there were several errors associated with the FRV 1FW540 digital upgrade work that were reasonably within the licensees ability to foresee and that should have been prevented, the inspectors determined that the performance deficiency involved did not rise to the level of being of more than minor safety significance and, as such, did not constitute a documentable finding. Additionally, no violations of NRC requirements were identified by the inspectors. Following their review, the inspectors concluded that the licensees identification of the issue had been timely and that the actions the licensee had taken to troubleshoot the condition had been reasonable and appropriate. Additionally, the inspectors concluded that the licensee had established corrective actions to address the issue that were appropriate for its safety significance and that could reasonably be expected to resolve the issue.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 17, 2019, the inspectors presented the integrated inspection results to the Plant Manager, Mr. J. Keenan, and other members of the licensee staff.
- On August 23, 2019, the inspectors presented the licensed operator requalification program inspection results inspection results to Ms. M. Marchionda, the Site Vice President, and other members of the licensee staff.
- On October 3, 2019, the inspectors presented the Exit Meeting for EP Inspection per IP 71114, Attachment 4 inspection results to Mr. L. Baker, the Emergency Preparedness Fleet Programs Manager, and other members of the licensee staff.
- On October 16, 2019, the inspectors presented the licensed operator requalification program inspection results and SLIV violation characterization inspection results to Ms. M. Marchionda, the Site Vice President, and other members of the licensee staff.
THIRD PARTY REVIEWS
As discussed in IMC 0611, Section 13.01, the inspectors completed a review of the report issued by the World Association of Nuclear Operators (WANO) for the most recent periodic plant evaluation performed at the Braidwood Station during April 2019.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.04Q Corrective Action
Documents
1047235
346 V 21 Rust and Dry Deposits on Stair Stringer and Floor
03/24/2010
1047255
343-0 (+8 FT) V-23 Stains and Mineral Deposits on Hanger
03/24/2010
1047650
Dry Brown Stains and Deposits on Concrete Wall in U2 CWA 03/25/2010
1047660
Repair Grout Seal in 364-0 Slab Near X/23
03/25/2010
267934
Cannot Remove Breaker from 1A SI Pump Cubicle
07/30/2019
276875
2SI8807A has Evidence of Packing Leak
09/05/2019
278048
Braidwood LR W/O Commitments Require Tighter Scrutiny
09/20/2019
Corrective Action
Documents
Resulting from
Inspection
267077
MCC 131X2 Cubicle C Rear Door Found not Latched
07/25/2019
277092
2CV206 Dry Boric Acid Leakage
09/05/2019
Drawings
M-136
Diagram of Safety Injection Unit 2
BR
M-61
Diagram of Safety Injection Unit 1
BJ
M-62
Diagram of Residual Heat Removal
BR
Procedures
BwOP RH-5
RH System Startup for Recirculation
BwOP RH-E1
Electrical Lineup Unit 1 - 1ARH Train
BwOP RH-M1
Operating Mechanical Lineup Unit 1 - 1A RH Train
BwOP S1-M1
Operating Mechanical Lineup Unit 1
BwOP SI-1
Safety Injection System Startup
BwOP SI-E1
Electrical Lineup - Unit 1 Operating
BwOP SI-E2
Electrical Lineup - Unit 2 Operating
BwOP SI-M2
Operating Mechanical Lineup Unit 2
Work Orders
1746544
Unit 2 - Area 7 Maintenance Rule Inspection Aux Bldg. 346
06/15/2015
4898247
IST for 2SI8919A/B/8922A/8926 - ASME Surveillance
Requirements for 2SI01PA
05/31/2019
4906921
IST for 2SI8919A/B/8922B/8926 - ASME Surveillance
Requirements for 2SI01PB
06/20/2019
4931599
U2 ECCS Venting and Valve Alignment Quarterly
09/10/2019
71111.05Q Corrective Action
Documents
Resulting from
262586
Cable Tray Wires Exceed Cable Tray Boundary
07/08/2019
262586
Cable Tray Wires Exceed Cable Tray Boundary
07/08/2019
263390
Broken Conduit
07/11/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Inspection
263390
Broken Conduit
07/11/2019
263659
Scaffold Tie Off to Structure Broke - Div 12 ESF Room
07/11/2019
263659
Scaffold Tie Off to Structure Broke - Division 12 Engineered
Safety Features Switchgear Room
07/12/2019
263917
Degraded Fire Hose Station
07/13/2019
265224
NRC ID: Appendix R Light not Directed at Equipment
07/18/2019
Fire Plans
Pre-Fire Plan 41
SWGA 426 Division 12 ESF Switchgear Room FZ5.1-1
Pre-Fire Plan 42
SWGA 426 Division 22 ESF Switchgear Room FZ5.1-2
Pre-Fire Plan 43
SWGA 426 Division 11 ESF Switchgear Room - FZ 5.2-1
Pre-Fire Plan 44
SWGA 426 Division 21 ESF Switchgear Room
Pre-Fire Plan 45
SWGA 451 Unit 1, Non-ESF Switchgear Room - FZ 5.3-1
Pre-Fire Plan 46
Fire Zone 5.3-2, Unit 2 Non-Engineered Safety Features
Switchgear Room
Pre-Fire Plan 47
Fire Zone 5.4-1, Division 12 Miscellaneous Electrical
Equipment Room and Battery Room
Pre-Fire Plan 48
Fire Zone 5.4-2, Division 22 Miscellaneous Electrical
Equipment Room and Battery Room
Procedures
BwAP 1110-1
Fire Protection Program System Requirements
BwAP 1110-3
Plant Barrier Impairment Program
BwOP PBI-1
Plant Barrier Impairment Program Pre-Evaluated Barrier
Matrix
Plant Barrier Control Program
High Risk Fire Area Identification
ER_BR-600-1069
Site List of High Risk Fire Areas - Braidwood Unit 1 and
Unit 2
Communications
Fire Prevention for Hot Work
Fire Protection System Impairment Control
Pre-Fire Plan Manual
Control of Transient Combustible Material
Corrective Action
Documents
4033220
VC Room Floor Drain Backed Up
08/18/2017
Drawings
Auxiliary Plumbing Flow Diagram
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
BwMS 3350-004
Watertight Door Surveillance
Work Orders
4749961
Inspection of Watertight Doors
11/01/2018
Corrective Action
Documents
TRNG: Performance EP Failure (DEP)
07/25/2017
TRNG: Performance EP Failure (DEP)
03/14/2018
Multiple Losses of ESF Bus 141 during 1A Diesel Generator
Sequence Testing in A1R20
04/19/2018
Roll-up and ECAP Request for Fuel Handling Issues During
A1R20
05/01/2018
Unit 1 Manual Reactor Trip due to Lowering Steam
Generator Level
06/04/2018
LORT TSA Failure (Isolate WS Flooding)
06/13/2018
Ir 4173301
NRC Biennial Exam Answer Choice Distribution
09/14/2018
Two DEP Failures of an Evaluated Simulator Scenario
03/26/2019
Crew Failure During OBE
05/28/2019
Missed NRC Notification Within 30-Day Requirement for
License Drop
06/26/2019
Update Dispatch Spreadsheet for IC Resets
08/06/2017
MST will not Reset
09/27/2017
Tuning the Feed System for Ovation
11/28/2018
Issues in CV System
06/20/2019
Enhancements to the MFW System Responses
07/25/2019
Corrective Action
Documents
Resulting from
Inspection
Extent of Condition of Operator License Maintenance
Review
08/27/2019
OP-AA-105-102, Attachment 1 Not Complete for 1st Quarter
2019
08/21/2019
Miscellaneous
2-
A.G.
Reactivation of License Log
05/11/2018
2-
D.B.
Reactivation of License Log
04/07/2018
2-
G.L.
Reactivation of License Log
2/14/2017
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2-J.L.
Reactivation of License Log
04/06/2018
2-J.P.
Reactivation of License Log
10/11/2017
2-
M.N.
Reactivation of License Log
01/01/2018
Scenario Guide
BR-5
Respond to a MS Line Break Inside Containment with
Miscellaneous Malfunctions
08/13/2019
Scenario Guide
BR-8
Respond to an RCS LOCA with Miscellaneous Malfunctions
08/20/2019
Simulator
Scenario Based
Testing
Scenario Number 18-1 NRC 2
05/07/2019
Simulator
Scenario Based
Testing
Braidwood Post-Event Trip of MWP
2/15/2018
Simulator
Scenario Based
Testing
Reactivity Scenario 1 / 18-1
08/20/2018
Simulator
Scenario Based
Testing
Braidwood Moderator Temp. Coefficient of Reactivity Att. 10
of TQ-AA-306, Cycle 21 with Plant Data Added
07/15/2018
Simulator
Scenario Based
Testing
Braidwood Rod Worth Reactivity Att. 11 of TQ-AA-306,
Cycle 21 with Plant Data Added
07/15/2018
Simulator
Scenario Based
Testing
Braidwood PWR Boron Coefficient of Reactivity Att. 12 of
TQ-AA-306, Cycle 21 Testing
01/15/2018
Simulator
Scenario Based
Testing
Braidwood PWR Approach to Criticality Using Boric Acid, Att.
of TQ-AA-306, Cycle 21 Testing
01/15/2018
Simulator
Scenario Based
Braidwood PWR Xenon Worths Att. 13 of TQ-AA-306,
Cycle 21
07/15/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Testing
Simulator
Scenario Based
Testing
Braidwood PWR Approach to Criticality with Boric Acid Att.
of TQ-AA-306, Cycle 21
07/21/2018
Simulator
Scenario Based
Testing
Braidwood Approach to Critical with Rods Att. 17 of
TQ-AA-306, Cycle 21 Testing
01/06/2018
Simulator
Scenario Based
Testing
Braidwood 2019 Annual Operating Test Scenario BR-5
08/12/2019
Simulator
Scenario Based
Testing
Braidwood 2019 Annual Operating Test Scenario BR-18
08/12/2019
Simulator Test
PMT SWR 135325, Issue in CV System
06/18/2019
TQ-BR-302-0107
Braidwood Transient Test 2, Simultaneous Trip of All Main
Feedwater Pumps, Cycle 21 Testing
TQ-BR-302-0110
Braidwood Transient Test 5, Trip of Any Single Reactor
Coolant Pump, Cycle 21 Testing
TQ-BR-302-0113
Braidwood Transient Test 8, LBLOCA with LOOP, Cycle 21
Testing
TQ-BR-302-0115
Braidwood Transient Test 10, Slow Primary Depress due to
Open PORV W/out Charging Pumps, Cycle 21 Testing
Procedures
NRC ACTIVE LICENSE MAINTENANCE
OP-BR-102-106
Operator Response Time Program at Braidwood Station
Scenario Guide
BR-18
Respond to a Main Steam Header Break and Miscellaneous
Malfunctions
08/21/2019
Scenario Guide
BR-25
Respond to a Vapor Space LOCA and Miscellaneous
Malfunctions
08/14/2019
Operator Training Programs
CONDUCT OF SIMULATOR TRAINING AND EVALUATION
EXAMINATION SECURITY AND ADMINISTRATION
Self-Assessments AR 4217716
Pre-NRC 71111.11 Inspection Licensed Operator
Requalification Training Assessment
07/18/2019
71111.11Q Corrective Action
255332
Main Control Room Alarm Sensitivity Review
06/07/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
266841
Unit 1 Power Ascension Delayed Due to Beacon
Uncertainties
07/25/2019
Miscellaneous
Reactivity
Maneuver Plan
BR1C21
Braidwood 1 Cycle 21 DC Ground Repair
07/23/2019
Reactivity
Maneuver Plan
BR1C21-09.0
Braidwood 1 Cycle 21 Coastdown
09/17/2019
Procedures
1BwGP 100-4
Power Decension
BwOP CD/CB-2
Condensate/Condensate Booster System Shutdown
BwOP FW-2
Shutdown of a Turbine-Driven Main Feedwater Pump
BwOP FW-30
Feedwater Regulating Valve Base Load Operation
OP-AA-101-111-
1001
Operations Standards and Expectations
Operator Fundamentals
OP-AA-101-113-
1006
4.0 Crew Critique Guidelines
Watch-Standing Proactices
OP-AA-103-102-
1001
Strategies for Successful Transient Mitigation
Operation of Plant Equipment
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
Reactivity Management
Systematic Approach to Training Process Description
Operator Training Program
Conduct of Simulator Training and Evaluation
Examination Security and Administration
Simulator Management
TQ-BR-201-0113
Braidwood Training Department Simulator Examination
Security Actions
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
28777
Braidwood Lessons Learned from Byron Feedwater Pump
Trip
04/26/2005
0331256
A2R11LL - 2B Feedwater Pump Lube Oil System
Troubleshooting
05/03/2005
29045
2B Feedwater Pump Oil Pressure Up Light Anomaly -
2FW01PB
20/09/2008
29046
Lesson Learned - 2B Feedwater Pump Oil Pump Auto Start
10/09/2008
1059245
Anomalies Observed During the Start of the 2B TDFW Pump
Oil
05/14/2010
1071520
Replace 2B Feedwater Pump Lube Oil Pressure Switch
05/20/2010
1071521
Replace 2B Feedwater Pump Lube Oil Pressure Switch
05/20/2010
1660140
B4 Trend Code: 2PS-FW203 Reset Out of Tolerance High
05/14/2014
4192076
2B Feedwater Pump Emergency Oil Pump Auto Started
11/06/2018
264965
Erratic Annunciators During Shiftly Test
07/18/2019
266428
Unexpected Alarm
07/23/2019
267503
2B Feedwater Pump Emergency Oil Pump Auto Started
07/28/2019
267874
Annunciator Box 1-17 Does Not Test Correctly
07/29/2019
Drawings
20E-2-4030FW22
Schematic Diagram Steam Generator Feedwater Pump 2B
Turbine Oil Pumps 2FW01PB-A, 2FW01PB-B
J
20E-2-4030FW23
Schematic Diagram Steam Generator Feedwater Pump 2B
Tubine Emergency Oil Pump 2FW01PB-C
F
M-152
Manufacturers Supplemental Diagram Steam Generator
Feed Pump Turbine Oil System
Y
Procedures
BwOP DC-23-111 125V DC Bus 111/113 Ground Detection
BwOP FW-10
Operation of a Turbine Driven Main Feedwater Pump Lube
Oil System
BwOP FW-23
Swapping Feedwater Pumps
Maintenance Rule Functions - Safety Significan
Classification
Maintenance Rule Implementation per NEI 18-10
Maintenance Rule 18 - 10 - Scoping
Maintenance Rule 18 - 10 - Failure Definitions
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Maintenance Rule 18 - 10 - Performance Monitoring and
Dispositioning Between (a)(1) and (a)(2)
Work Orders
0958686
Perform Post-Maintenance Disassembled Inspection of
Turbine Feed Pump
06/09/2008
1354739
Replace 2B Feedwater Pump Lube Oil Pressure Switch
11/08/2012
1354740
Replace 2B Feedwater Pump Lube Oil Pressure Switch
11/08/2012
Corrective Action
Documents
209878
DC Bus 111 Ground Coming in with 1PL01J Panel Check
01/10/2019
248185
DC Bus 111 Ground
05/11/2019
264965
Erratic Annunciators During Shiftly Test
07/18/2019
265545
Unexpected Annunciator 1-21-D6: DC Bus 111 Ground
07/19/2019
266428
Unexpected Alarm
07/23/2019
267874
Annunciator Box 1-17 does not Test Correctly
07/29/2019
270540
DC System Trend IR (January 2014 - July 2019)
08/08/2019
270893
2TO5337A Inspection Revealed Foreign Material
08/10/2019
272352
Annunciator 1-2-E4 Did Not Clear as Expected
08/16/2019
274648
Unit 1 Annunciator Horn Troubleshooting Learnings
08/27/2019
281976
1FW520 Status on 1PL100J Status Needs Verification
09/25/2019
Drawings
20E-2-4030FW23
Steam Generator Feedwater Pump 2B Turbine Emergency
Oil Pump 2FW01PB-C
F
Procedures
1BwOSR 0.1-
1,2,3
Unit 1 Modes 1, 2, and 3 Shiftly and Daily Operating
Surveillance
1BwOSR
5.5.8.FW-1
Unit One Main and Bypass Feedwater Regulating Valves
and Tempering Flow Control Valves Fail Safe Test 18 Month
Surveillance
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
BwIP 1FW520
Calibration of 1B Steam Generator Feedwater Flow
Regulating Valve (FW)
BwOP DC-E2
Electrical Lineup - Unit 1 Operating - 125V DC Division 11
Conduct of Troubleshooting
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Work Orders
4850789
2B Feedwater Pump Oil Filter Differential Pressure High
08/09/2019
20701
DC Bus 111 Ground
07/23/2019
4962887
1FW520: Calibrate Feedback Unit, Positioner, and Perform
Flowscan
09/24/2019
4963345
1FW520: Replace Digital Valve Controller and Flowscan
Feedwater Regulating Valve
09/24/2019
Calculations
2-7720-B140
Secondary Side Small Nozzles ASME Level A/B/C/D
Analysis
2-7720-SR-2
Byron and Braidwood Replacement Steam Generator
Transient Analysis Report - Section 5, 5% Power Uprate
(3600.6 MWt)
Calibration
Records
1464960
CCP: Tape on Spare Fuse Holders in 1DC12J
01/20/2013
Corrective Action
Documents
29453
Fukushima Walkdown Found Duct Tape on Fuse Holder
Covers
10/21/2012
1464956
CCP: Tape on Spare Fuse Holders in 1DC10J
01/20/2013
1464959
CCP: Tape on Spare Fuse Holders in 1DC11J
01/20/2013
1464959
CCP: Tape on Spare Fuse Holders in 1DC11J
01/20/2013
1464961
CCP: Tape on Spare Fuse Holder in 1DC13J
01/20/2013
1464962
CCP: Tape on Spare Fuse Holders in 2DC11J
01/20/2013
1464964
CCP: Tape on Spare Fuse Holders in 2DC12J
01/20/2013
1464965
CCP: Tape on Spare Fuse Holders in 2DC13J
10/20/2013
4016750
1A SX Pump Significantly Weaker than 1B SX Pump
05/31/2017
4155768
2B SX Strainer Stuck in Continuous Backwash
07/14/2018
4168621
Issues Closing 1SX046A
08/30/2018
25240
Review of Byron IR 4185973 Feedwater Regulating Valve
Travel Transducers
03/01/2019
250599
Request WR to Replace 1FW540 Travel Transducer During
Window
05/21/2019
257124
1A SX Pp Strainer is Backwashing Excessively
06/15/2019
259918
Noisy and Slowly Increasing Demand on 1FW540 Controller
06/27/2019
269369
1A SX Pp Strainer is Backwashing Excessively
08/03/2019
270893
FME: 2TO5337A Inspection Revealed FM
08/10/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
270913
FME: 2TO5313A Relief Valve Cap Gasket Missing
08/10/2019
272160
4.0 Critique 2B TDFWP Work Window
08/15/2019
272501
Notification of Code Nonconformance for Replacement
08/16/2019
272834
DC 112 Specific Gravity Deviation High
08/18/2019
274831
1A SX Pp Strainer is Backwashing Excessively
08/27/2019
275530
Schedule WO to Perform Follow-up UT on Section of
1SX93AB
08/29/2019
276343
ACB 1424 Took Multiple Attempts to Close 1AP06EQ
09/03/2019
279078
2AF01PB - 2B Auxiliary Feedwater Pump Diesel - Abnormal
Noise While Running
09/13/2019
279222
Documentation of 2B Auxiliary Feedwater Pump Shaft
Condition
09/13/2019
279236
Lot Part - Woodruff Key for 2B Auxiliary Feedwater Pump
09/14/2019
279748
Extent of Condition Following IR 4279078
09/16/2019
Corrective Action
Documents
Resulting from
Inspection
273062
NRC Identified Duct Tape on Spare Fuses in 2DC11J
08/19/2019
Drawings
Installation Notes for Electrical Equipment
V
Synchronizing Diagram 4160 SWGR & Diesel Gen. 1A & 1B
J
Internal Wiring Diagram 125V DC Fuse PNL 2DC11J-ESF-
Part 1
C
Internal Wiring Diagram 125V DC Fuse PNL 2DC11J-ESF
- Part 2
D
20E001
Steam Generator Arrangement
20E214
Steam Drum Assemble - Stage 1
M-42
Diagram of Essential Service Water Units 1 & 2
BE
M152
Manufacturers Supplemental Diagram Steam Generator
Feed Pump Turbine Oil System
Y
Engineering
Changes
391045
Engineering Chang Evaluating Use of Non-Metallic Tie
Wraps on Spare Fuse Holders
29229
TCCP to Temporarily Jumper Out Cell 2 of ESF Battery 112
to Allow 125 VDC ESF Battery 112 Operation with 57 Cells
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
BRW-S-2019-58
Temporarily Jumper Out Cell #2 of ESF Battery 112 to Allow
25 VDC ESF Battery 112 Operation With 57 Cells
Engineering
Evaluations
396312
Evaluation for Determining RCFC Operability When SX
Discharge Header Pressure Low Alarm is in
29019
Lost Parts Evaluation 2B FW Turbine Oil System Foreign
Material
29021
Losst Part Evaluation for Adjustment Gasket Within
2TO5313A
PP_SX-10
2SX01PA - 2BwOSR 5.5.8SX.6A - IST Pump Evaluation
Form
09/22/2016
Procedures
1BwOA PRI-8
Essential Service Water Malfunction Unit 1
107
1BwOL 3.8.1
LCOAR AC Sources - Operating - Tech Spec LCO 3.8.1
1BwOSR 3.6.6.2
Reactor Containment Fan Cooler Surveillance
1BwOSR 3.7.8.1
Unit One Essential Service Water System Surveillance
1BwOSR 3.8.1.8-
SAT 242-2 Crosstie to Bus 142 and DG 1B Crosstie to Bus
2 Surveillance
1BwOSR 3.8.6.5-
Unit One 125V DC ESF Battery Bank 112 Operability
Surveillance
BRW-97-0384-
E/BYR97-204
25 VDC Battery Sizing Calculation Braidwood Only Key
Calc
BwAR 1-2-A2
SX Pump Discharge Header Pressure Low - Alarm No. 1-2-
A2
BWAR 1-2-C2
SX Trainer dP High - Alarm No. 1-2-C2
BwOP DC-2T1
Battery Capacity Talbe for 125V DC ESF Battery
BwOP DC-5-112
25 DC ESF Battery 112 Equalization
BYR97-
406/BRW-97-
0965-M
RCFC Performance Curve Calculation
Lost Parts Evaluations
Administrative Requirements for Inservice Testing
Risk Management Documentation
Risk Assessments of Missed or Deficient Surveillances
MA-MW-726-605
25 Volt DC ESF Battery Cell Jumpering
0A
OP-AA-106-101-
Operational Decision Making Process
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1006
Adverse Condition Monitoring and Contingency Planning
Operability Determinations (CM-1)
Work Orders
1960165
U1 SX System Flow Balance Surveillance
01/16/2016
4849480
2B FW Pump Oil Filter dP High
11/02/2018
4850789
2B FW Pump OIl Filter dP High
08/10/2019
27972
LR-IST for 1SX002A - ASME Surveillance Requirements for
1A Essential Service Water Pump
08/27/2019
Corrective Action
Documents
269037
0FP03PB Stuffing Box Leak
08/02/2109
272278
RD Project - U1 Condenser Cosmetic Damage
08/15/2019
278254
Intentionally Abbreviated Maintenance: 2P-VE001LOOP
09/11/2019
Engineering
Changes
24901
Augmented Cooling for Control Rod Drive Cabinets Unit 1 -
50.59 Screening No. BRW-S-2018-82
24903
Augmented Cooling for Control Rod Drive Cabinets Unit 2 -
50.59 Screening No. BRW-S-2018-66
Corrective Action
Documents
4107548
Erratic Reading on 0TI-FP8023
2/23/2018
266039
GOCAR BwAP 1110-1A2 Past 7 Days for -B DDFP
07/22/2019
269424
Diesel Fire Pump Battery Connection
08/03/2019
270013
0TI-FP8047 Reading Erratic and Inaccurate
08/06/2019
270088
2DG5228A Missing Plug Resulted in Small Air Leak
08/07/2019
270279
Flange Leak at Discharge of 0FP775B on Return to Service
08/07/2019
270387
Small Leak Found at FP03PB Fitting
08/08/2019
273569
1SX2080B Valve Difficult to Operate - Unable to Fully Close
08/21/2019
Procedures
0BwOS FP.2.1.E-
1B
0B Fire Protection Pump Flow and Pressure Test
0BwOS
FP.2.2.M-2
Diesel Driven Fire Pump Surveillance
0BwOS FP.3.3.E-
0B Fire Pump NFPA Test
1BwOSR
5.5.8.SI-10B
Group A IST Requirements for 1B Safety Injection Pump
(1SI01PB)
1BwOSR
Test Operation of ECCS Motor Operated Valves
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
5.5.8.SI-12
Surveillance
2BwOSR
5.5.8.CS-3B
Comprehensive Full Flow Test for 2B Containment Spray
Pump (2CS01PB) and Check Valves 2CS003B, 2CS011B
BwAP 1110-qA2
Fire Suppression Water Supply Required Compensatory
Measures Action Response
BwAR 0-38-C7
Fire Pump Diesel Trouble
BwOP CS-5
Containment Spray System Recirdulation to the RWST
BwOP SI-1
Safety Injection System Startup
BwOP SI-2
Safety Injection System Shutdown
Work Orders
1764793
Change Greae in Coupling and Perform Inspection of
Coupling Internals
08/2/2019
1843557
Grease Inspection Grade of Grease 3 - 1SI8923B
08/21/2019
1898770
1SI01PB-M Perform Static Barrier Testing
08/21/2019
1914717
1SI01PB Weeping Oil Leak on Oil Return Line
08/21/2019
4613459
1SI01PB Replace Oil Breathers and Mark Oil Level S/G
08/21/2019
4654936
Rebuild Actuator, Reg/Replace Elastomers
08/15/2019
4671383
2FSV-CS010B Replace Solenoid Valve
08/15/2019
4680012
Weeping Oil Leak at 1TE-SI002D
08/21/2019
4758895
Failed PMTS: 2A DG Fuel Leak 3-5 DPM
08/07/2019
4843529
Overhaul DDFP per Pump & Motor Plan in 2019
08/06/2019
4917400
IST-1RH01PB ASME Group A Test & CC-1SI8958B
07/26/2019
20701
DC Bus 111 Ground
07/23/2019
21630
2A DG - 2019 Pre 2 Year Work Window Engine Analysis
Results
08/07/2019
25636
IST - For 2CS003B/11B ASME Surveillance Requirements
for 2CS01PB & Check Valves
07/15/2019
4943770
LR-IST-2A D/G Operability Monthly
08/07/2019
4947232
LR-0B Fire Protection Pump Flow and Pressure Test
08/07/2019
Corrective Action
Documents
269965
Water Found in Vacuum Breaker #3 Vault, No Active Leak
08/06/2019
269970
Water Found in Vacuum Breaker #11 Vault, No Active Leak
08/06/2019
275218
Corrosion Found Inside Radiator Opening of 0FX03PA
08/28/2019
275829
0BwOS FX-9 Improvement Opportunity
08/30/2019
276486
Work Request Needed to Fabricate Flex Discharge Manifold
09/03/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Operability
Evaluations
BwOP DG-1
Diesel Generator Alignment to Standby Condition
Procedures
0BwOS CW-1
Unit Common Circulating Water System Blowdown Line
Inspection
0BwOS FX-9
Flex Pump Flow Surveillance
1BwOSR 3.7.5.4-
Unit One Diesel Driven Auxiliary Feedwater Pump
Surveillance
2BwOSR 3.8.1.2-
2A Diesel Generator Operability Surveillance
2BwOSR 3.8.1.8-
SAT 142-1 Crosstie to Bus 241 and Diesel Generator 2A
Crosstie to Bus 141 Surveillance
BwOP AF-7
Auxiliary Feedwater Pump _B (Diesel) Startup on Recirc
BwOP AF-7T1
Diesel Driven Auxiliary Feedwater Pump Operating Log
BwOP AF-8
Auxiliary Feedwater Pump _B (Diesel) Shutdown
BwOP DG-11
Diesel Generator Startup and Operation
BwOP DG-12
Diesel Generator Shutdown
Work Orders
4674064
Perform 3 Y Inspection/Maintenance on #1 Flex Pump
08/29/2019
24690
SAT 142-1 Crosstie to Bus 241 18-Month Surveillance
09/04/2019
4933550
2A EDG Operability Monthly
07/10/2019
4943151
LR-1B AF Pump Monthly Surveillance Run
08/16/2019
4947149
U0 CW Blowdown Vacuum Breaker Inspection
08/06/2019
Miscellaneous
Evaluation 18-45
Exelon Nuclear Standardized Radiological Emergency Plan,
Revision 30
2/14/2019
71151
Miscellaneous
NRC
Performance
Indicator Data;
Mitigating
Systems
Mitigating System Performance Index for Heat Removal
Systems
07/01/2018 -
06/30/2019
NRC
Performance
Indicator Data;
Mitigating
Systems
Mitigating System Performance Index for Residual Heat
Removal Systems
07/01/2018 -
06/30/2019
NRC
Mitigating System Performance Index for Cooling Water
07/01/2018 -
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Performance
Indicator Data;
Mitigating
Systems
Systems
06/30/2019
Procedures
Collecting and Reporting of NRC Performance Indicator Data 15
Mitigating System Performance Index Data Acquisition and
Reporting
Root Cause Analysis Manual
Corrective Action
Documents
209878
DC Bus 111 Ground Coming in with 1PL01J Panel Check
01/10/2019
248185
DC Bus 111 Ground
05/11/2019
265545
Unexpected Annunciator 1-21-D6: DC Bus 111 Ground
07/19/2019
Procedures
Quality Assurance Topical Report (QATR)
Issue Identification and Screening Process
Corrective Action Program (CAP) Procedure
Corrective Action Program Evaluation Manual
Work Orders
4659603
Install EC 620239: Upgrade Feedwater Regulating Valve
Positioner to Digital
04/11/2018
Corrective Action
Documents
281429
Unit 1 Reactor Trip on Lo-2 Steam Generator Level in 1B
09/23/2019
281460
Unit 1 - N-36 Reading Higher than Expected
09/23/2019
281465
Unit 1 Post-Accident Neutron Monitor 1NI-NR006A Failed
Low
09/23/2019
281521
Various Radiation Monitors Spiking During Reactor Trip
09/23/2019
281548
4.0 Critique for Unit 1 Reactor Trip
09/23/2019
281624
1ZC-FW520 Unable to Communicate with Digital Valve
Controller
09/24/2019
Procedures
Post Transient Review
13