IR 05000255/2021002

Integrated Inspection Report 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

August 10, 2021

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, Signed by Dickson, Billy on 08/10/21 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: DPR-20 Report Number: 05000255/2021002 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 Enclosure

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.

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,

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 Type Designation Description or Title Revision or

Procedure Date

71111.01 Corrective Action CR-PLP-2021- V-21H During Restoration and Test Run of Fan in Screen 04/15/2021

Documents 1026 House Discovered V-21A, Intake Structure Fresh Air Fan,

Had Excessive Noise and Vibration

Miscellaneous PLP-RPT-15- Palisades Nuclear Plant Flooding Hazard Re-Evaluation 1

00010 Report

Procedures AOP-38 Acts of Nature 20

Work Orders 52926621-01 Warm Weather Checklist 05/18/2021

71111.04 Corrective Action CR-PLP-2021- Penetration FZ-0547 has not been Included in the Procedure 04/20/2021

Documents 01074 DBD-7.10

CR-PLP-2021- Bi-weekly Inspection of ED-02 (Station Battery #2) Under 05/17/2021

01307 Work Order 557033-01

CR-PLP-2021- Bi-weekly Inspection of ED-02 (Station Battery #2) Cell #43 06/15/2021

01575

Procedures SOP-12 Feedwater 85

SOP-15 Service Water System 71

SOP-3 Engineered Safeguards 108

SOP-30 Station Power System 93

71111.05 Corrective Action CR-PLP-2-21- EVI-1603 P-41 Battery Bank 2 Voltmeter Displaying Erratic 04/20/2021

Documents 01081 Readings

CR-PLP-2021- South Wall of the 1-1 Diesel Generator Room was Found to 04/16/2021

01038 be Starting to Separate from the Barrier

CR-PLP-2021- FZ-0547 has Cracking Along the Face of the Seal Where it 04/20/2021

01073 Meets the Penetrating Conduits

CR-PLP-2021- Received Alarm EK-1148 Fire System Panel C-48, C-47A/B 05/19/2021

01342 or C C-49 Off Normal Unexpectedly

CR-PLP-2021- Door-187, DIG 1-2 K-68 Day Tank Room Entrance 05/20/2021

01357

Corrective Action CR-PLP-2021- **NRC Identified** During Plant Tour, NRC Resident 06/01/2021

Documents 01457 Identified a Small Amount of Fuel Oil (FO) on the Floor

Resulting from Underneath MV-DE515, D/G 1-1 FO Day Tank T-25A Drain

Inspection

Fire Plans Fire Area 28 West Engineered Safeguards Room, Elevation 570' 5

Inspection Type Designation Description or Title Revision or

Procedure Date

Pre-Fire Plan 10 East Engineered Safeguards Room, Elevation 570' 5

Pre-Fire Plan 24 Auxiliary Feedwater Pump Room, Elevation 571' 5

71111.07A Corrective Action CR-PLP-2021- During the Performance of WO 52878638-01 (Eddy Current 05/18/2021

Documents 01330 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

Miscellaneous Sample Heat Exchanger Visual Inspection Datasheet 05/18/2021

Procedures 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

SEP-HX-PLP-001 Supplemental HX Visual Inspection Checklist, EDG Jacket 05/17/2021

Water Cooler

Work Orders 52904475-01 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

2904475-03 E-22B, 1-2 D/G Jacket Water Cooler, Contingency Task for 05/18/2021

Tube Plugging

71111.11Q Procedures PLSEG-LOR- AOP Scenario 1

21A-04

71111.12 Miscellaneous System Health Report 04/01/2016-

06/30/2016

System Health Report 10/01/2016-

2/31/2016

Functional Failure EX-10; Main Transformer Winding Temperature had Risen 10/08/2019

Determination to 81.5 Degrees

Form

PLP-RPT-12- Maintenance Rule Scoping Document; 4160 Volt AC Power 4

00026,

System Health HAC - 4160 Volt AC System 05/10/2021

Report Q2 - 2020

System Health HAC - 4160 Volt AC System 05/10/2021

Report Q2 -2019

System Health HAC - 4160 Volt AC System 05/10/2021

Report Q4 - 2019

System Health HAC - 4160 Volt AC System 05/10/2021

Inspection Type Designation Description or Title Revision or

Procedure Date

Report Q4 - 2020

71111.13 Corrective Action CR-PLP-2021- The Integrated Risk for the Operations PMT on the CV- 04/22/2021

Documents 01104 2056, Letdown to VCT or VDT, Following the Seat Load

Adjustment, was Inadvertently Made High Risk for the

Radiological Conditions

CR-PLP-2021- CV-0608, Moisture Separator Drain Tank T-5 Level Control, 05/04/2021

212 Cycling

CR-PLP-2021- CRDM Cooling Fan Tripped Unexpectedly 05/11/2021

257

CR-PLP-2021- MCC-10 Trip Troubleshooting Under Work Order 562603-01 05/12/2021

260

CR-PLP-2021- The Control Room Entered AOP-38, Acts of Nature, Due to 05/12/2021

265 Notification of a Geo Magnetic Storm with a K Index of 7

CR-PLP-2021- CRD-23 is About 185 Degrees and has Been Stable Since 05/13/2021

273 Restoring the CRDM Cooling Fan

CR-PLP-2021- During the 480 Volt MCC-10 There was a Subsequent Rise 05/13/2021

282 in Pressure Seen in the P-50B Seal Upper and Middle State

Pressures

Miscellaneous White Paper CV-2056, Letdown to Volume Control Tank (VCT) or 04/14/2021

Vacuum Degassifier Tank (Diversion Valve) White Paper

Procedures EN-OP-119 Protected Equipment Postings 13

SOP-10 Extraction and Heater Drain Systems 41

71111.15 Calculations 0098-0168-01 Cracked EDG Turbocharger Support - Past Operability 1

Evaluation

0098-0169-02 Cracked EDG Turbocharger Support - Past Operability 0

Evaluation

Corrective Action CR-PLP-2019- During the Performance of QO-21A Smoke was Noted 06/10/2019

Documents 02323 Rising from the Inboard Pump Bearing Area

CR-PLP-2019- Two Cracks were Found in a Turbocharger Support Weld on 10/09/2019

4060 Emergency Diesel Generator 1-1 (K-6A)

CR-PLP-2021- During Inspection of K-6A, 1-1 Emergency Diesel Generator, 02/18/2021

00458 Identified Cracking on the West Side of the South Vertical

Turbocharger Support

CR-PLP-2021- Q-Level Fuses were Found to be Installed in a Safety 03/30/2021

Inspection Type Designation Description or Title Revision or

Procedure Date

00864 Related Application

CR-PLP-2021- During Real Time Clock Battery Replacement, Evidence of 04/13/2021

00999 Connector Melting was Identified on Plastic Battery

Connector (Molex)

CR-PLP-2021- Possible Weld Leakage from Valve Body to Pipe Welded 04/22/2021

01107 Connection on CV-2056 (Letdown to CT-54 or DVT T-57

CR-PLP-2021- Possible Weld Leakage from Valve Body to Pipe Welded 04/22/2021

01107 Connection on CV-2056

CR-PLP-2021- Indications Were Found on the Discharge to the VCT Weld 04/23/2021

01114 for CV-2056

CR-PLP-2021- Steam Driven Auxiliary Feed Pump Outboard Pump Bearing 05/12/2021

264 Seal Leakage was Observed at 48 DPM

CR-PLP-2021- Repack of P-8B (Steam Driven Auxiliary Feed Pump) per 05/13/2021

272 Work Order 562621-01

CR-PLP-2021- During QO-21B Performed Under WO 52961213 a Speed 05/13/2021

274 Adjustment was Required per Step 5.9.2

CR-PLP-2021- During the First Post-Maintenance Test Start of K-6B, the 05/19/2021

01340 Fuel Oil Secondary Filter Diff Pressure Rose from 6 PSID

(EOG was Unloaded) to 13 PSID

CR-PLP-2021- K-6B Fuel Oil Differential Pressure Indicator, was Out of 05/19/2021

01341 Spec High

CR-PLP-2021- CV-3042 (Safety Injection Tank T-82A Pressure Control) 06/07/2021

01504 Showing Dual Indication

CR-PLP-2021- VT-2 Inspection of Test RT-71 M 06/10/2021

01537

CR-PLP-2021- VT-2 Inspection Portion of RT-71 M 06/20/2021

01538

CR-PLP-2021- Right Train SIRWT Outlet Flange 06/10/2021

01543

CR-PLP-2021- T-58 SIRW Tank Roof Walk Down with the NRC 06/15/2021

01576

Drawings M-201, Sheet 1 Piping and Instrument Diagram, Primary Coolant System 86

M-202, Sheet 1A Piping and Instrument Diagram, Chemical and Volume 62

Control System

Inspection Type Designation Description or Title Revision or

Procedure Date

Engineering 11-PAL-0051 Evaluation/Screening of Boric Acid Leakage, T-58, Safety 1

Evaluations Injection Refueling Water Tank

Miscellaneous Design Basis Low Pressure Safety Injection 12

Document 2.01

Design Basis High Pressure Safety Injection 11

Document 2.02

Design Basis Reactor Protective System Safety Injection Signal 7

Document 2.05 Anticipated Transient Without Scram

Procedures EN-MA-125 Troubleshooting Control of Maintenance Activities 04/22/2021

EPS-E-9 Use of Portable DC Ground Fault Detection System 10

Work Orders 00526705-02 P-8B: Restore/PMT After Outboard Packing Maintenance 11/13/2019

00559905-01 DC Bus #2 Ground Volt Indicator Repair 04/14/2021

71111.19 Corrective Action CR-PLP-2021- Adjusted the Spring to Increase Seat Load by the Plug While 04/22/2021

Documents 01108 the Valve is in the "Extended" Position

CR-PLP-2021- During RO-97, Auxiliary Feedwater System Automatic 05/12/2021

267 Initiation Test Procedure, Operations Could Not Perform

Step 5.6.12

CR-PLP-2021- Repack on P-8B, Steam Driven Auxiliary Feedwater Pump, 05/12/2021

271 Under WO 00562621-01

CR-PLP-2021- Field Voltage was Identified Out of Normal Range at 139 05/20/2021

01348 Volts for both the 1 Hour and 2 Hour Data Points

CR-PLP-2021- Received Alarm EK-0603D Nuclear-OT Power Deviation / T- 05/24/2021

01369 Inlet Off-Normal / Calculator Trouble Channel A

Unexpectedly

Engineering EC-89735 "Line Kill" Leak Repair for MV-BW826, Steam Generator (E- 0

Changes 50B) Feed Regulator Bypass Valve (CV-0734) Outlet Drain

EC-89736 "Line Kill" Leak Repair for MV-FW827, Steam Generator (E- 0

50A) Feed Regulator Bypass Valve (DV-0735) Inlet Drain

EC-89911 Temporary Leak Repair of Leaking Pipe-to-Tube Adapter 0

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

Work Orders 553840-01 LC-0608 Not Controlling Within Proper Band 05/11/2021

553840-02 LC-0608 Not Controlling Within Proper Band (Prep Work) 12/21/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.22 Corrective Action CR-PLP-2021- Operations Could Not Perform Step 5.6.12 to Restore HS- 05/12/2021

Documents 01267 0522B to Auto

Miscellaneous 4Q2019 NRC Performance Indicators Unplanned Power 10/01/2019 -

Changes per 7000 Critical Hours (IE03) 12/31/2019

Procedures QO-1 Safety Injection System 71

QO-42 Inservice Testing of Shutdown Cooling Control Valves 25

RE-131 Diesel Generator 1-1 Load Reject 04/05/2021

RO-128-2 Diesel Generator 1-2 24-Hour Load Run 32

Work Orders 52904702-01 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

2904788-01 FLEX Standby PM: P-1003 Three Yr Performance Test 04/06/2021

(FSB A)

71124.02 Radiation Work 2020-0417 RWP Review Package for Primary Coolant Pump 03/02/2021

Permits (RWPs) Replacement

20-0430 RWP Review Package for Fuel Moves 10/01/2020

20-0434 RWP Review Package for reactor reassembly 02/05/2021

20-0450 RWP Review Package for Reactor Head Nozzle Inspection 10/13/2020

and Repair

71151 Miscellaneous 4Q2019 NRC Performance Indicators Safety System 10/01/2019 -

Functional Failures (MS05) 12/31/2019

1Q2020 NRC Performance Indicators Safety System 01/01/2020 -

Functional Failures (MS05) 03/31/2020

2Q2020 NRC Performance Indicators Safety System 04/01/2020 -

Functional Failures (MS05) 06/31/2020

3Q2020 NRC Performance Indicators Safety System 07/01/2020 -

Functional Failures (MS05) 09/30/2020

4Q2020 NRC Performance Indicators Safety System 10/01/2020 -

Functional Failures (MS05) 12/31/2020

1Q2020 NRC Performance indicators Unplanned Power 01/01/2020 -

Changes per 7000 Critical Hours (IE03) 03/31/2020

2Q2020 NRC Performance Indicators Unplanned Power 04/01/2020 -

Changes per 7000 Critical Hours (IE03) 06/30/2020

3Q2020 NRC Performance Indicators Unplanned Power 07/01/2020 -

Inspection Type Designation Description or Title Revision or

Procedure Date

Changes per 7000 Critical Hours (IE03) 09/30/2020

4Q2020 NRC Performance Indicators Unplanned Power 10/01/2020 -

Changes per 7000 Critical Hours (IE03) 12/31/2020

71152 Corrective Action CR-PLP-2021- CRDM Cooling Fan was Lost 05/13/2021

Documents 01273

CR-PLP-2021- On May 14, 2021, the PCS Unidentified Leak Rate was 05/14/2021

287 Measured to be 0.091 GPM

CR-PLP-2021- The PCS Unidentified Leak Rate was Measured at 0.082 05/17/2021

01308 GPM

CR-PLP-2021- CRDM Seal Leakage was Measured at 110m/min 05/17/2021

01322

CR-PLP-2021- During QI-9, Reactor Protective Trip Units, Additional Action 06/02/2021

01460 Taken During a Procedure Step

Miscellaneous February 2021 DPRM/APRM Report 02/2021

Adverse CRD-23, Control Rod Drive Mechanism, Elevated Leakoff 05/17/2021

Condition Temperature

Monitoring Plan

Procedures Procedure No. PCS Leakage Decision Flowchart 6

4.19, Attachment

16