IR 05000255/2021002
| ML21222A118 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/10/2021 |
| From: | Billy Dickson NRC/RGN-III/DRP/B2 |
| To: | Corbin D Entergy Nuclear Operations |
| References | |
| IR 2021002 | |
| Download: ML21222A118 (18) | |
Text
SUBJECT:
PALISADES NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000255/2021002
Dear Mr. Corbin:
On June 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palisades Nuclear Plant. On July 20, 2021, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
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, Billy C. Dickson, Jr., Chief Branch 2 Division of Reactor Projects Docket No. 05000255 License No. DPR-20
Enclosure:
As stated
Inspection Report
Docket Number:
05000255
License Number:
Report Number:
Enterprise Identifier:
I-2021-002-0101
Licensee:
Entergy Nuclear Operations, Inc.
Facility:
Palisades Nuclear Plant
Location:
Covert, MI
Inspection Dates:
April 01, 2021 to June 30, 2021
Inspectors:
P. Laflamme, Senior Resident Inspector
V. Myers, Senior Health Physicist
C. St. Peters, Resident Inspector
Approved By:
Billy C. Dickson, Jr., Chief
Branch 2
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Palisades Nuclear Plant, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
The plant began the inspection period at rated thermal power and remained at or near rated thermal 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 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.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week, increasing the amount of time on site as local COVID-19 conditions permitted.
As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities; and completed on site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of extreme heat for the following systems:
Switchyard, 1-2 startup transformer, and service water system on May 19, 2021
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding on May 28, 2021.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)1-2 Startup transformer on April 19, 2021
- (2) Right Train low pressure safety injection (SI) on April 16, 2021
- (3) P-8C auxiliary feedwater (AFW) pump system on April 26, 2021
- (4) Station 1 battery system on June 10, 2021
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Left Train critical service water system on May 5, 2021.
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Fire Area 10: east engineered safeguards room, elevation 570' on April 9, 2021
- (2) Fire Area 24: AFW pump room elevation, 571' on April 26, 2021
- (3) Fire Area 28: west engineered safeguards room, elevation 570' on May 27, 2021
- (4) Fire Areas 5 & 7: 1-1 diesel generator and fuel oil day tank rooms, elevation 590' on June 1, 2021
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) 1-2 emergency diesel generator (EDG) jacket water cooling heat exchanger on June 23, 2021
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 Control Room during QO-1 SI actuation test (elevated risk evolution), Left Train, on May 26, 2021.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated PLSEG-LOR-21A-04; Abnormal Operating Procedure (AOP) Scenario on May 11, 2021.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Radiation monitoring system on April 7, 2021 (2)4160V alternating current (HAC) system on June 8, 2021
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Yellow risk for planned high pressure SI system maintenance and testing on April 14, 2021
- (2) Elevated risk due to letdown system isolation for planned maintenance and testing on April 22, 2021
- (3) Elevated risk for planned component cooling water system testing on April 29, 2021
- (4) Emergent work activities associated with main feed pump suction pressure oscillations due to CV-0608, T-5 level control valve, increased cycling, on May 6, 2021
- (5) Yellow risk for planned AFW system testing coupled with predicted geomagnetic storm disturbance on May 12, 2021
- (6) Elevated risk due to controller relay coil failure rendering all four atmospheric steam dump valves inoperable and subsequent repair on June 16, 2021
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)1-1 EDG turbocharger support crack evaluation on April 5, 2021
- (2) D channel thermal margin monitor evaluation on April 15, 2021
- (3) Direct current (DC) bus 2 ground detection Q-4 fuse circuitry evaluation on April 27, 2021
- (4) Chemical and volume control system piping weld indication evaluation on May 11, 2021
- (5) AFW P-8B outboard packing evaluation on May 17, 2021
- (6) CV-3042 safety injection tank (SIT) T-82A pressure control evaluation on June 8, 2021
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (7 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) CV-2056, volume control tank (VCT) to vacuum degassifier tank (VDT) divert valve maintenance and testing on May 3, 2021
- (2) CV-0608 T-5 level control valve and testing on May 11, 2021
- (3) EDG 1-2 planned governor replacement and testing on May 19, 2021
- (4) AFW P-8B packing replacement and testing on May 24, 2021
- (5) MO-3012, low pressure SI to reactor coolant 2A maintenance and testing on May 25, 2021
- (6) Steam generator A and B feed regulator bypass valve drain piping repairs and testing on May 28, 2021
- (7) Thermal margin monitoring system Channel A repair and testing on June 3, 2021
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) RO-128 EDG 1-2 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> run, on April 19-20, 2021 (2)1-1 EDG load reject surveillance test on April 12, 2021
- (3) RO-127: AFW system 18-Month test on May 13, 2021
- (4) QO-1: SI actuation system test - right train on May 26, 2021
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) QO-42: Shutdown cooling valves inservice test on June 15, 2021
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) FLEX standby PM: P-1003 Three Year Performance Test on April 14, 2021
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
- (1) The inspectors observed an emergency preparedness (EP) drill on June 2,
RADIATION SAFETY
71124.02 - Occupational ALARA Planning and Controls
Radiological Work Planning (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensees radiological work planning for the following work activities.
- (1) Primary coolant pump seal replacement under Radiation Work Permit (RWP)2020-0417
- (2) Fuel moves under RWP 2020-0430
- (3) Reactor vessel reassembly under RWP 2020-0434
- (4) Reactor head nozzle inspection and repair under RWP 2020-0450 Verification of Dose Estimates and Exposure Tracking Systems (IP Section 03.02) (4 Samples)
The inspectors evaluated dose estimates and exposure tracking for the following work activities.
- (1) Primary coolant pump seal replacement under RWP 2020-0417
- (2) Fuel moves under RWP 2020-0430
- (3) Reactor vessel reassembly under RWP 2020-0434
- (4) Reactor head nozzle inspection and repair under RWP 2020-0450
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02)===
- (1) Unit 1 (April 1, 2020 - March 31, 2021)
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (1 Sample)
- (1) Unit 1 (April 1, 2020 - March 31, 2021)
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees Corrective Action Program (CAP) for potential adverse trends with a focus on low level human performance issues that might be indicative of a more significant safety issue during the period from January 1, 2021 to June 30, 2021.
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Elevated unidentified primary coolant system (PCS) leakage condition evaluation as documented in CR-PLP-2021-1066 during the week of June 21,
INSPECTION RESULTS
Observation: Semiannual Trend Review 71152 The inspectors review focused on human performance issues and considered the results of daily inspector CAP item screening and licensee trending efforts. The inspectors review nominally considered the 6 months of January 2021 through June 2021, although some examples expanded beyond those dates when warranted by the scope of the trend.
The inspectors reviewed condition reports, trend reports, and human performance evaluations to address performance oversight at the site. During the inspection period, the inspectors noted a few challenges where low-level human performance errors occurred in multiple departments, including Operations, Training, and Maintenance. Examples include electricians losing control of jumpers multiple times, one of which resulted in the site entering an AOP due to an arc flash, unsecured training exams, workers not following procedure adherence while bypassing the reactor protection system during a surveillance test, and two near misses of dropped objects while working at heights. Although the above examples did not challenge safety function or equipment reliability, these issues illustrated a decline in using human performance tools, potentially impacting nuclear safety.
The licensee appropriately entered these issues into the CAP and completed timely evaluations addressing each challenge listed above. Corrective actions included training, site-wide communications reinforcing standards and expectations, and a re-emphasis on the following human performance tools: pre-job briefs; procedure use and adherence; and verification and validation activities. The inspectors determined that the corrective actions taken to date appeared to address the identified gaps effectively and plan to continue to evaluate these actions during routine observations and inspections.
Observation: Primary Coolant System Unidentified Leakage Evaluation 71152 The inspectors reviewed the events, circumstances, and causal evaluation associated with elevated primary coolant system (PCS) unidentified leakage rates that occurred in April of 2021. Their efforts included assessing the licensee's adverse condition monitoring plan, troubleshooting, failure mode analysis, trending, and aggregate review activities.
Additionally, the inspectors reviewed leakage trends, equipment condition assessments for the letdown system, primary coolant pump (PCP) seal leak off system, and control rod drive mechanism (CRDM) leakage collection manifold, along with monthly containment tour results and containment sump level monitoring. The inspectors also interviewed operators, maintenance workers, and engineering personnel to complete their assessment efforts.
In their review, the inspectors noted that most of the elevated unidentified leakage was accounted for by known leakage from the PCP seal leak off system, CRDM leakage collection manifold, and the letdown system to vacuum degassifier tank (VDT) via the VCT divergent valve bypass (3-way flow valve). Since the above sources cannot be quantitatively measured individually on a routine basis, the collective measurements must administratively be quantified as unidentified combined leakage as required by station procedures. As a corrective action, the licensee performed adjustments on the VCT divergent valve and periodically isolated the VDT while conducting daily unidentified leakage surveillance tests to better quantify and trend unidentified leakage rates. Therefore, since the licensee confirmed the sources of elevated leakage in both measure and location and associated corrective actions addressed the condition, the inspectors concluded the licensee actions taken were timely and effective commensurate with safety significance. In addition, the inspectors compared and contrasted their review of a similar leakage evaluation as documented in Palisades Inspection Report (IR) 2020001. In their current review, the inspectors noted that although the sources of leakage were the same, the leakage path, quantity, duration, and initiation of each source discussed above differed for the April 2021 occurrence.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On July 20, 2021, the inspectors presented the integrated inspection results to Mr. D. Corbin, Vice President, Operations, and other members of the licensee staff.
On April 2, 2021, the inspectors presented the radiation protection inspection results to Mr. D. Corbin, Vice President, Operations, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-PLP-2021-
26
V-21H During Restoration and Test Run of Fan in Screen
House Discovered V-21A, Intake Structure Fresh Air Fan,
Had Excessive Noise and Vibration
04/15/2021
Miscellaneous
PLP-RPT-15-
00010
Palisades Nuclear Plant Flooding Hazard Re-Evaluation
Report
Procedures
Acts of Nature
Work Orders
2926621-01
Warm Weather Checklist
05/18/2021
CR-PLP-2021-
01074
Penetration FZ-0547 has not been Included in the Procedure
DBD-7.10
04/20/2021
CR-PLP-2021-
01307
Bi-weekly Inspection of ED-02 (Station Battery #2) Under
05/17/2021
Corrective Action
Documents
CR-PLP-2021-
01575
Bi-weekly Inspection of ED-02 (Station Battery #2) Cell #43
06/15/2021
SOP-12
SOP-15
Service Water System
SOP-3
Engineered Safeguards
108
Procedures
SOP-30
Station Power System
CR-PLP-2-21-
01081
EVI-1603 P-41 Battery Bank 2 Voltmeter Displaying Erratic
Readings
04/20/2021
CR-PLP-2021-
01038
South Wall of the 1-1 Diesel Generator Room was Found to
be Starting to Separate from the Barrier
04/16/2021
CR-PLP-2021-
01073
FZ-0547 has Cracking Along the Face of the Seal Where it
Meets the Penetrating Conduits
04/20/2021
CR-PLP-2021-
01342
Received Alarm EK-1148 Fire System Panel C-48, C-47A/B
or C C-49 Off Normal Unexpectedly
05/19/2021
Corrective Action
Documents
CR-PLP-2021-
01357
Door-187, DIG 1-2 K-68 Day Tank Room Entrance
05/20/2021
Corrective Action
Documents
Resulting from
Inspection
CR-PLP-2021-
01457
- NRC Identified** During Plant Tour, NRC Resident
Identified a Small Amount of Fuel Oil (FO) on the Floor
Underneath MV-DE515, D/G 1-1 FO Day Tank T-25A Drain
06/01/2021
Fire Plans
Fire Area 28
West Engineered Safeguards Room, Elevation 570'
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Pre-Fire Plan 10
East Engineered Safeguards Room, Elevation 570'
Pre-Fire Plan 24
Auxiliary Feedwater Pump Room, Elevation 571'
Corrective Action
Documents
CR-PLP-2021-
01330
During the Performance of WO 52878638-01 (Eddy Current
Testing of E-22B (EOG 1-2 Jacket Water Heat Exchanger))
it was Identified that Degradation in the Form of Pitting was
Occurring in E-22B
05/18/2021
Miscellaneous
Sample Heat Exchanger Visual Inspection Datasheet
05/18/2021
CEP-NDE-0902
ASME Section XI VT-2 Examination Record, E-22B, E-13B
05/19/2021
CH 1.11
MIC Control Program Inspection Report
05/17/2021
Procedures
SEP-HX-PLP-001
Supplemental HX Visual Inspection Checklist, EDG Jacket
Water Cooler
05/17/2021
2904475-01
K-6B 1-2 D/G, 24M (1 Cycle) PM
05/18/2021
2904475-02
K-6B; PMT: 24M (1 Cycle) PM of 1-2 D/G (OPS)
05/19/2021
Work Orders
2904475-03
E-22B, 1-2 D/G Jacket Water Cooler, Contingency Task for
Tube Plugging
05/18/2021
Procedures
PLSEG-LOR-
AOP Scenario
System Health Report
04/01/2016-
06/30/2016
System Health Report
10/01/2016-
2/31/2016
Functional Failure
Determination
Form
EX-10; Main Transformer Winding Temperature had Risen
to 81.5 Degrees
10/08/2019
PLP-RPT-12-
00026,
Maintenance Rule Scoping Document; 4160 Volt AC Power
System Health
Report Q2 - 2020
HAC - 4160 Volt AC System
05/10/2021
System Health
Report Q2 -2019
HAC - 4160 Volt AC System
05/10/2021
System Health
Report Q4 - 2019
HAC - 4160 Volt AC System
05/10/2021
Miscellaneous
System Health
HAC - 4160 Volt AC System
05/10/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Report Q4 - 2020
CR-PLP-2021-
01104
The Integrated Risk for the Operations PMT on the CV-
2056, Letdown to VCT or VDT, Following the Seat Load
Adjustment, was Inadvertently Made High Risk for the
Radiological Conditions
04/22/2021
CR-PLP-2021-
212
CV-0608, Moisture Separator Drain Tank T-5 Level Control,
Cycling
05/04/2021
CR-PLP-2021-
257
CRDM Cooling Fan Tripped Unexpectedly
05/11/2021
CR-PLP-2021-
260
MCC-10 Trip Troubleshooting Under Work Order 562603-01
05/12/2021
CR-PLP-2021-
265
The Control Room Entered AOP-38, Acts of Nature, Due to
Notification of a Geo Magnetic Storm with a K Index of 7
05/12/2021
CR-PLP-2021-
273
CRD-23 is About 185 Degrees and has Been Stable Since
Restoring the CRDM Cooling Fan
05/13/2021
Corrective Action
Documents
CR-PLP-2021-
282
During the 480 Volt MCC-10 There was a Subsequent Rise
in Pressure Seen in the P-50B Seal Upper and Middle State
Pressures
05/13/2021
Miscellaneous
White Paper
CV-2056, Letdown to Volume Control Tank (VCT) or
Vacuum Degassifier Tank (Diversion Valve) White Paper
04/14/2021
Protected Equipment Postings
Procedures
SOP-10
Extraction and Heater Drain Systems
0098-0168-01
Cracked EDG Turbocharger Support - Past Operability
Evaluation
Calculations
0098-0169-02
Cracked EDG Turbocharger Support - Past Operability
Evaluation
CR-PLP-2019-
2323
During the Performance of QO-21A Smoke was Noted
Rising from the Inboard Pump Bearing Area
06/10/2019
CR-PLP-2019-
4060
Two Cracks were Found in a Turbocharger Support Weld on
Emergency Diesel Generator 1-1 (K-6A)
10/09/2019
CR-PLP-2021-
00458
During Inspection of K-6A, 1-1 Emergency Diesel Generator,
Identified Cracking on the West Side of the South Vertical
Turbocharger Support
2/18/2021
Corrective Action
Documents
CR-PLP-2021-
Q-Level Fuses were Found to be Installed in a Safety
03/30/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
00864
Related Application
CR-PLP-2021-
00999
During Real Time Clock Battery Replacement, Evidence of
Connector Melting was Identified on Plastic Battery
Connector (Molex)
04/13/2021
CR-PLP-2021-
01107
Possible Weld Leakage from Valve Body to Pipe Welded
Connection on CV-2056 (Letdown to CT-54 or DVT T-57
04/22/2021
CR-PLP-2021-
01107
Possible Weld Leakage from Valve Body to Pipe Welded
Connection on CV-2056
04/22/2021
CR-PLP-2021-
01114
Indications Were Found on the Discharge to the VCT Weld
for CV-2056
04/23/2021
CR-PLP-2021-
264
Steam Driven Auxiliary Feed Pump Outboard Pump Bearing
Seal Leakage was Observed at 48 DPM
05/12/2021
CR-PLP-2021-
272
Repack of P-8B (Steam Driven Auxiliary Feed Pump) per
05/13/2021
CR-PLP-2021-
274
During QO-21B Performed Under WO 52961213 a Speed
Adjustment was Required per Step 5.9.2
05/13/2021
CR-PLP-2021-
01340
During the First Post-Maintenance Test Start of K-6B, the
Fuel Oil Secondary Filter Diff Pressure Rose from 6 PSID
(EOG was Unloaded) to 13 PSID
05/19/2021
CR-PLP-2021-
01341
K-6B Fuel Oil Differential Pressure Indicator, was Out of
Spec High
05/19/2021
CR-PLP-2021-
01504
CV-3042 (Safety Injection Tank T-82A Pressure Control)
Showing Dual Indication
06/07/2021
CR-PLP-2021-
01537
VT-2 Inspection of Test RT-71 M
06/10/2021
CR-PLP-2021-
01538
VT-2 Inspection Portion of RT-71 M
06/20/2021
CR-PLP-2021-
01543
Right Train SIRWT Outlet Flange
06/10/2021
CR-PLP-2021-
01576
T-58 SIRW Tank Roof Walk Down with the NRC
06/15/2021
M-201, Sheet 1
Piping and Instrument Diagram, Primary Coolant System
Drawings
M-202, Sheet 1A
Piping and Instrument Diagram, Chemical and Volume
Control System
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Evaluations
11-PAL-0051
Evaluation/Screening of Boric Acid Leakage, T-58, Safety
Injection Refueling Water Tank
Design Basis
Document 2.01
Low Pressure Safety Injection
Design Basis
Document 2.02
High Pressure Safety Injection
Miscellaneous
Design Basis
Document 2.05
Reactor Protective System Safety Injection Signal
Anticipated Transient Without Scram
Troubleshooting Control of Maintenance Activities
04/22/2021
Procedures
EPS-E-9
Use of Portable DC Ground Fault Detection System
00526705-02
P-8B: Restore/PMT After Outboard Packing Maintenance
11/13/2019
Work Orders
00559905-01
DC Bus #2 Ground Volt Indicator Repair
04/14/2021
CR-PLP-2021-
01108
Adjusted the Spring to Increase Seat Load by the Plug While
the Valve is in the "Extended" Position
04/22/2021
CR-PLP-2021-
267
During RO-97, Auxiliary Feedwater System Automatic
Initiation Test Procedure, Operations Could Not Perform
Step 5.6.12
05/12/2021
CR-PLP-2021-
271
Repack on P-8B, Steam Driven Auxiliary Feedwater Pump,
Under WO 00562621-01
05/12/2021
CR-PLP-2021-
01348
Field Voltage was Identified Out of Normal Range at 139
Volts for both the 1 Hour and 2 Hour Data Points
05/20/2021
Corrective Action
Documents
CR-PLP-2021-
01369
Received Alarm EK-0603D Nuclear-OT Power Deviation / T-
Inlet Off-Normal / Calculator Trouble Channel A
Unexpectedly
05/24/2021
"Line Kill" Leak Repair for MV-BW826, Steam Generator (E-
50B) Feed Regulator Bypass Valve (CV-0734) Outlet Drain
"Line Kill" Leak Repair for MV-FW827, Steam Generator (E-
50A) Feed Regulator Bypass Valve (DV-0735) Inlet Drain
Engineering
Changes
Temporary Leak Repair of Leaking Pipe-to-Tube Adapter
Joint Downstream of MV-CD623, P-1A Suction Flow Xmtr
FT-0711 Hi Side Root
Procedures
QO-21
Inservice Test Procedure Auxiliary Feedwater Pumps
05/13/2021
553840-01
LC-0608 Not Controlling Within Proper Band
05/11/2021
Work Orders
553840-02
LC-0608 Not Controlling Within Proper Band (Prep Work)
2/21/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-PLP-2021-
267
Operations Could Not Perform Step 5.6.12 to Restore HS-
22B to Auto
05/12/2021
Miscellaneous
4Q2019 NRC Performance Indicators Unplanned Power
Changes per 7000 Critical Hours (IE03)
10/01/2019 -
2/31/2019
QO-1
Safety Injection System
QO-42
Inservice Testing of Shutdown Cooling Control Valves
RE-131
Diesel Generator 1-1 Load Reject
04/05/2021
Procedures
RO-128-2
Diesel Generator 1-2 24-Hour Load Run
2904702-01
FLEX Standby PM: K-1 Flex Three Year Load Test
04/06/2021
2904703-01
FLEX Standby PM: K-2 Flex Three Year Load Test
04/16/2021
2904787-01
Standby PM: P-990 Three Yr Performance Test (FSB B)
04/06/2021
Work Orders
2904788-01
FLEX Standby PM: P-1003 Three Yr Performance Test
(FSB A)
04/06/2021
20-0417
RWP Review Package for Primary Coolant Pump
Replacement
03/02/2021
20-0430
RWP Review Package for Fuel Moves
10/01/2020
20-0434
RWP Review Package for reactor reassembly
2/05/2021
Radiation Work
Permits (RWPs)
20-0450
RWP Review Package for Reactor Head Nozzle Inspection
and Repair
10/13/2020
4Q2019 NRC Performance Indicators Safety System
Functional Failures (MS05)
10/01/2019 -
2/31/2019
1Q2020 NRC Performance Indicators Safety System
Functional Failures (MS05)
01/01/2020 -
03/31/2020
2Q2020 NRC Performance Indicators Safety System
Functional Failures (MS05)
04/01/2020 -
06/31/2020
3Q2020 NRC Performance Indicators Safety System
Functional Failures (MS05)
07/01/2020 -
09/30/2020
4Q2020 NRC Performance Indicators Safety System
Functional Failures (MS05)
10/01/2020 -
2/31/2020
1Q2020 NRC Performance indicators Unplanned Power
Changes per 7000 Critical Hours (IE03)
01/01/2020 -
03/31/2020
2Q2020 NRC Performance Indicators Unplanned Power
Changes per 7000 Critical Hours (IE03)
04/01/2020 -
06/30/2020
71151
Miscellaneous
3Q2020 NRC Performance Indicators Unplanned Power
07/01/2020 -
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Changes per 7000 Critical Hours (IE03)
09/30/2020
4Q2020 NRC Performance Indicators Unplanned Power
Changes per 7000 Critical Hours (IE03)
10/01/2020 -
2/31/2020
CR-PLP-2021-
273
CRDM Cooling Fan was Lost
05/13/2021
CR-PLP-2021-
287
On May 14, 2021, the PCS Unidentified Leak Rate was
Measured to be 0.091 GPM
05/14/2021
CR-PLP-2021-
01308
The PCS Unidentified Leak Rate was Measured at 0.082
GPM
05/17/2021
CR-PLP-2021-
01322
CRDM Seal Leakage was Measured at 110m/min
05/17/2021
Corrective Action
Documents
CR-PLP-2021-
01460
During QI-9, Reactor Protective Trip Units, Additional Action
Taken During a Procedure Step
06/02/2021
February 2021 DPRM/APRM Report
2/2021
Miscellaneous
Adverse
Condition
Monitoring Plan
CRD-23, Control Rod Drive Mechanism, Elevated Leakoff
Temperature
05/17/2021
Procedures
Procedure No.
4.19, Attachment
PCS Leakage Decision Flowchart
6