IR 05000255/2020004

Integrated Inspection Report 05000255/2020004

ML21043A019
Person / Time
Site:	Palisades
Issue date:	02/11/2021
From:	Billy Dickson NRC/RGN-III/DRP/B2
To:	Corbin D Entergy Nuclear Operations
References
IR 2020004
Download: ML21043A019 (25)

Text

February 11, 2021

SUBJECT:

PALISADES NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000255/2020004

Dear Mr. Corbin:

On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palisades Nuclear Plant. On January 21, 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.

One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. 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 the 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 Palisades.

If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region III; and the NRC Resident Inspector at Palisades. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

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: 05000255/2020004 Enterprise Identifier: I-2020-004-0030 Licensee: Entergy Nuclear Operations, Inc.

Facility: Palisades Nuclear Plant Location: Covert, MI Inspection Dates: October 01, 2020 to December 31, 2020 Inspectors: E. Fernandez, Reactor Inspector G. Hansen, Senior Emergency Preparedness Inspector 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, 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 to Follow Procedure Results in an Arc to Ground and Entry into Abnormal Operating Procedure (AOP) 36 "Loss of Component Cooling Water (CCW)" Cornerstone Significance Cross-Cutting Report Aspect Section Initiating Events Green [H.11] - 71152 NCV 05000255/2020004-01 Challenge the Open/Closed Unknown A self-revealed Green finding and associated non-cited violation (NCV) of Technical Specification 5.4.1a occurred on September 9, 2020, when the licensee failed to follow plant procedure EN-MA-101, "Conduct of Maintenance." Specifically, the licensee's failure to correctly implement step 5.3.2c of procedure EN-MA-101 resulted in the supervisor getting involved in the hands-on work. This resulted in an arc to ground of safety-related DC breaker 72-118, subsequent unanticipated opening of valve CV-0910 "CCW Supply to Containment" and valve CV-0911 "CCW from Containment" due to a loss of power, standby CCW pump start, and consequential tank T-3, "Component Cooling Water Surge Tank," level drop requiring entry into AOP-36, "Loss of Component Cooling Water (CCW)."

Additional Tracking Items

Type Issue Number Title Report Section Status LER 05000255/2020-002-00 LER 2020-002-00 for 71153 Closed Palisades Nuclear Plant,

Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations

PLANT STATUS

The plant began the inspection period shutdown in mode 6 for a refueling outage. On October 20, 2020, the plant was taken critical and successfully synced to the grid on October 21, 2020. The plant achieved rated thermal power on October 27, 2020, and remained at or near rated thermal power for the remainder 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 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 Disease 2019 (COVID-19), resident 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; conducted plant status activities as described in IMC 2515, Appendix D, Plant Status; observed risk-significant activities; and completed onsite portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or portions 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 onsite. 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 seasonal cold temperatures for the following systems on December 1, 2020

• Emergency diesel generators (EDGs)

• Spent fuel pool

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (3 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Component cooling water (CCW) on November 9, 2020

(2) Left train auxiliary feedwater (AFW) on November 17, 2020

(3) 7B service water pump system on November 24, 2020

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated system configurations during a complete walkdown of the 1D 2.4KV electrical bus system on December 11, 2020.

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) Station Battery Room, Fire Area 11, on November 16, 2020

(2) Station Battery Room, Fire Area 12, on November 16, 2020

(3) Mechanical Equipment Rooms, Fire Area 30, on November 23, 2020

(4) Mechanical Equipment Rooms, Fire Area 31, on November 23, 2020

Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the onsite fire brigade training and performance during an annual fire drill on December 3, 2020.

71111.06 - Flood Protection Measures

Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)

The inspectors evaluated internal flooding mitigation protections in the:

(1) 1C Switchgear Room on December 22, 2020

71111.07A - Heat Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1) VHX027A Engineering Safeguards Room cooling coil on December 4, 2020

71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)

(1) The inspectors documented a partial completion of this inspection procedure in inspection report 05000255/2020003. During this inspection period, the inspectors reviewed the licensees actions to address a flaw which was below recordable threshold during the last outage. The licensee reexamined the nozzle, identified the flaw had grown, and repaired the nozzle.

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 vacuum fill on October 15, 2020.

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated SER-406, Revision 2 on November 23, 2020.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (1 Sample)

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 during the week of December 14, 2020

Quality Control (IP Section 03.02) (1 Sample)

The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following SSC remains capable of performing its intended function:

(1) 125 VDC vital power system during the week of November 23, 2020

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (1 Sample)

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) Elevated risk during planned maintenance on battery charger #2 and right train AFW flow control valve testing on October 26, 2020.

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) Technical specification sodium tetraborate basket weight evaluation on October 7, 2020

(2) CV-0826 past operability evaluation on October 9, 2020

(3) Core exit thermocouple cabling evaluation on October 21, 2020

(4) Service water to containment air cooling system evaluation on November 20, 2020

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 temporary or permanent modifications:

(1) Engineering Change (EC) 84697: Thermal margin monitor system channel D display replacement modification on December 17, 2020.

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:

(1) Control rod testing on October 28, 2020

(2) Control rod number 2 maintenance and testing on October 29, 2020

(3) Battery charger number 2 testing on November 18, 2020

(4) P-52C CCW pump maintenance and testing on December 16, 2020

(5) P-55C charging pump maintenance and testing on December 22, 2020

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated refueling outage 1R27 activities from August 30 to October 27, 2020.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) Quarterly 7C service water pump test on November 19, 2020

Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) Local leak rate testing on November 12, 2020

71114.04 - Emergency Action Level and Emergency Plan Changes

Inspection Review (IP Section 02.01-02.03) (1 Sample)

(1) The inspectors completed an evaluation of submitted Emergency Action Level and Emergency Plan changes on December 10, 2020. This evaluation does not constitute NRC approval.

71114.06 - Drill Evaluation

Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01)

(1 Sample)

(1) Evaluated exercise on October 27, 2020

Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

The inspectors evaluated:

(1) Tabletop exercise on November 10,

71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &

Transportation

Waste Characterization and Classification (IP Section 03.03)

The inspectors evaluated the licensee's characterization of the following radioactive waste shipments:

(1) 2020-RW-003; Clean Radwaste Filters

(2) 2020-RW-004; Primary Purification Filter

(3) 2020-RW-006; Primary Purification Resin

Shipping Records (IP Section 03.05) (3 Samples)

The inspectors evaluated the following non-excepted radioactive material shipments through a record review:

(1) 2020-RW-003; Clean Radwaste Filters Shipped as LSA-II

(2) 2020-RW-004; Primary Purification Filter Shipped as Type B

(3) 2020-RW-006; Primary Purification Resin Shipped as Type B

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

MS06: Emergency AC Power Systems (IP Section 02.05) ===

(1) Unit 1 (October 1, 2019-September 30, 2020)

MS10: Cooling Water Support Systems (IP Section 02.09) (1 Sample)

(1) Unit 1 (October 1, 2019-September 30, 2020)

BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (1 Sample)

(1) Unit 1 (April 1, 2019-September 30, 2020)

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) April 1, 2019-September 30, 2020 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)

(1) April 1, 2019-September 30, 2020

71152 - Problem Identification and Resolution

Semiannual Trend Review (IP Section 02.02) (1 Sample)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends in equipment reliability that might be indicative of a more significant safety issue on December 10, 2020.

Annual Follow-up of Selected Issues (IP Section 02.03) (2 Samples)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) 1-2 EDG starting air system leak evaluation as documented in CR-PLP-2020-00239 on December 21, 2020

(2) Electrical maintenance near miss arc fault evaluation as documented in CR-PLP-2020-3261 on November 24, 2020

71153 - Follow-up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

The inspectors evaluated the following licensee event reports (LERs):

(1) LER 05000255/2020-002-00, Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations (ADAMS Accession No. ML20314A143). The inspectors determined that it was not reasonable to foresee or correct the cause discussed in the LER and therefore no performance deficiency was identified. The inspectors did not identify a violation of NRC requirements.

INSPECTION RESULTS

Failure to Follow Procedure Results in an Arc to Ground and Entry into Abnormal Operating Procedure (AOP) 36 "Loss of Component Cooling Water (CCW)"

Cornerstone Significance Cross-Cutting Report Aspect Section Initiating Events Green [H.11] - 71152 NCV 05000255/2020004-01 Challenge the Open/Closed Unknown A self-revealed Green finding and associated non-cited violation (NCV) of Technical Specification 5.4.1a occurred on September 9, 2020, when the licensee failed to follow plant procedure EN-MA-101, "Conduct of Maintenance." Specifically, the licensee's failure to correctly implement step 5.3.2c of procedure EN-MA-101 resulted in the supervisor getting involved in the hands-on work. This resulted in an arc to ground of safety-related DC breaker 72-118, subsequent unanticipated opening of valve CV-0910 "CCW Supply to Containment" and valve CV-0911 "CCW from Containment" due to a loss of power, standby CCW pump start, and consequential tank T-3, "Component Cooling Water Surge Tank," level drop requiring entry into AOP-36, "Loss of Component Cooling Water (CCW)."

Description:

On September 9, 2020, with the unit shutdown in mode 6, the site attempted to remove a temporary modification that powered up selected ED-11-2, 125 VDC Panel, breaker loads. In preparation to remove the jumper on 13-TV4 terminal 120 from a lug, a supervisor observing the work asked to take a closer look to help gather more information. As the supervisor looked, he accidentally touched a wire which contacted an energized component and caused an arc to ground. In their review, the inspectors noted that the supervisor helping to gather more information by getting involved in the hands-on work was contrary to step 5.3.2c of procedure EN-MA-101, which states, "ensure that the oversight role of the supervisor is maintained and not compromised by getting involved with the hands-on work." As a result, the arc to ground resulted in safety-related direct current (DC) breaker 72-118 tripping open.

The breaker opening resulted in the loss of the 125V DC power supplied to CCW containment isolation valves CV-0910 and CV-0911, which immediately opened per design.

This configuration change allowed the CCW system to fill a previously drained portion of CCW piping inside containment. The unanticipated CCW inventory movement resulted in CCW standby pump autostart, subsequent tank T-3 level drop to 2 percent, resultant low-level alarm in Control Room, and actuation of the autofill system per design. In response, the site entered AOP-36, "Loss of CCW," for tank T-3 low-level alarm and verified autofill system restored T-3 inventory to the normal level.

The inspectors reviewed the associated apparent cause analysis for the event, maintenance rule evaluation, control room logs, and interviewed operations, engineering, and maintenance personnel. In their review, the inspectors noted that CCW supply header pressure and temperature remained constant during the CCW system inventory movement and the autofill system functioned as designed. The inspectors also noted that the licensee determined the movement of CCW inventory to be a maintenance rule functional failure because the autofill system is not safety-related and could not be relied upon to mitigate the unanticipated movement of inventory. Specifically, the T-3 inventory capacity was significantly less than the volume of drained CCW piping inside containment, and the autofill system was not a credited makeup source. As a result, if the autofill system had failed to actuate, a loss of CCW net positive suction head to the CCW pumps would have likely occurred. Therefore, the inspectors concluded, the loss of DC and resultant movement of CCW inventory presented a potential challenge to the CCW system operability that could upset plant stability and challenge critical safety functions during shutdown operations.

Corrective Actions: The licensee entered AOP-36 "Loss of CCW," ensured water level was restored to tank T-3, and performed an apparent cause analysis (ACA) for the event. In addition, the licensee conducted a stand down with all electrical maintenance supervisors to discuss and reinforce supervisor roles and responsibilities.

Corrective Action References: CR-PLP-2020-3261, CR-PLP-2020-3262

Performance Assessment:

Performance Deficiency: The inspectors determined that the licensee's failure to ensure a supervisor stay in role and not get involved in the hands-on work of gathering information on a jumper the workers were attempting to remove in accordance with EN-MA-101 step 5.3.2c was a performance deficiency.

Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Human Performance attribute of the Initiating Events cornerstone and adversely affected the cornerstone objective to limit the likelihood of events that upset plant stability and challenge critical safety functions during shutdown as well as power operations.

Significance: The inspectors assessed the significance of the finding using Appendix G, Shutdown Safety SDP. Using IMC 0609, Appendix G, Attachment 1, Exhibit 2, the inspectors screened the finding as Green because it did not increase the likelihood of a shutdown initiating event, did not result in a loss of coolant or inventory, did not involve a loss of offsite power, did not involve a loss of residual heat removal or level control, and did not increase the likelihood of a fire, flood, or other external event.

Cross-Cutting Aspect: H.11 - Challenge the Unknown: Individuals stop when faced with uncertain conditions. Risks are evaluated and managed before proceeding. Specifically, the licensee did not stop work when they were unable to remove the jumper from the temporary modification. This resulted in the licensee supervisor performing hands-on data gathering which caused an energized component to make contact with a grounded component and the DC breaker tripping open.

Enforcement:

Violation: Technical Specification Section 5.4.1a requires, in part, that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February,1978. NRC Regulatory Guide 1.33, Revision 2, Appendix A, Section 1 addresses Administrative Procedures. The licensee established Procedure EN-MA-101, Revision 33 to address conduct of maintenance while performing work on safety-related equipment, including jumpers.

Contrary to the above, on September 9, 2020, the licensee failed to implement step 5.3.2c of EN-MA-101. Specifically, the licensee supervisor got involved in hands-on work which resulted in an arc to ground and DC breaker 72-118 tripping open. DC breaker 72-118 tripping open then opened two containment isolation valves, CV-0910 and CV-0911, which allowed water to fill a previously drained portion of CCW, T-3 low-level alarm, and entry into AOP-36.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Observation: 1-2 Emergency Diesel Generator Starting Air System Leak Causal 71152 Evaluation Review The inspectors reviewed the associated causal evaluation, extent of condition review, and corrective actions taken associated with an air leak identified on PCV-1490, "1-2 EDG 'B' Starting Air Pressure Control Valve." The inspectors noted the direct cause was improper diaphragm seating resulting from improper manufacturing/assembly at the manufacturer. In their review, the inspectors concluded that the air leak identification, causal evaluation, extent of condition, and subsequent valve replacement were all completed in a timely and effective manner commensurate with safety significance. No issues of significance were identified.

Observation: Semiannual Trend Review 71152 The inspectors' review focused on equipment reliability and considered the results of daily inspector Corrective Action Program (CAP) item screening and licensee trending efforts. The inspectors' review nominally considered the six months of July 2020 through December 2020, although some examples expanded beyond those dates when warranted by the trend's scope.

The inspectors reviewed condition reports, trend reports, and engineering calculations addressing human performance and equipment reliability at the site. During the inspection period, the NRC inspectors noted a few challenges to equipment reliability. Specifically, the inspectors observed and reviewed activities associated with the "B" primary coolant pump (PCP) seal degradation, elevated control rod drive (CRD) leakage trends and temperatures leading into the refueling outage, and "B" main feed pump (MFP) thrust bearing spurious elevated vibration alarms.

The inspectors noted that the licensee identified and monitored the PCP seal degradation.

Also, the inspectors noted that the licensee performed a weekly trend analysis of the seal pressures. Regarding the CRD leakage trends and temperatures leading into the refueling outage, the licensee monitored the parameters and then performed maintenance during the outage on the CRDs. The inspectors also noted for the B MFP thrust bearing vibration alarms that the licensee performed an engineering calculation and then a temporary modification to address the issue. Although these issues illustrated a challenge to equipment reliability, the inspectors did not identify an adverse trend during this assessment period.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

• On January 21, 2021, the inspectors presented the integrated inspection results to Mr. D. Corbin, Site Vice President Operations, and other members of the licensee staff.

• On November 19, 2020, the inspectors presented the radiation protection inspection results to Mr. D. Lucy, General Manager Plant Operations, and other members of the licensee staff.

• On December 10, 2020, the inspectors presented the emergency action level and emergency plan changes inspection results to Mr. D. Malone, Emergency Planning Manager, 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-2020- Notification from the National Weather Service of a High 11/14/2020

Documents 04621 Wind Warning for Van Buren County

CR-PLP-2020- Cold Weather Checklist-1 (SOP-23, Attachment 8) was 11/30/2020

04749 Submitted for the Official Record with Missing Signatures

CR-PLP-2020- During Rounds, NPO noticed V-32B, Screen House Roof 12/11/2020

04851 Vent Fan, Making Excessive Noise

Procedures SOP-23 Plant Heating System 64

71111.04 Corrective Action CR-PLP-2020- EX-02, Station Power Transformer No. 1-2 09/19/2020

Documents 03646

CR-PLP-2020- Received Alarm EK-0547, 125 Volt DC Bus Ground, 10/04/2020

03981 Unexpectedly

CR-PLP-2020- South End Ball of E-54A Surface Corrosion 10/04/2020

03983

CR-PLP-2020- CRD-18 (Control Rod Drive Mechanism) Seal Leak Off 10/27/2020

04389 Temperature

CR-PLP-2020- Primary Coolant Gas Vent System 10/27/2020

04390

CR-PLP-2020- V-24D, Diesel Generator Room Supply Fan 10/29/2020

04430

Corrective Action CR-PLP-2020- NRC Identified Some Wads of Insulation on Top of a Cable 12/17/2020

Documents 04912 Tray in "C" Switchgear Room

Resulting from

Inspection

Procedures SOP-12 Auxiliary Feedwater System Checklist 84

SOP-15 Service Water System Checklist 71

SOP-16 Component Cooling System Checklist 48

71111.05 Corrective Action CR-PLP-2020- During the Combined Fire and EP Medical Drill on 12/03/2020

Documents 04801 December 3rd, Objective Element L.2.1 was Rated Not

Observed

CR-PLP-2020- P-9B, Diesel Driven Fire Pump 12/11/2020

04861

Fire Plans Pre-Fire Plan Fire Battery Rooms Elevation 607' 6" 5

Inspection Type Designation Description or Title Revision or

Procedure Date

Area 11 & 12

Pre-Fire Plan Fire Mechanical Equipment Rooms 5

Area 30 & 31

Miscellaneous PLDRL-FBT-Fire 4th Quarter 2020 Fire Brigade Drill (Unannounced) Shift #1 12/03/2020

drill

PLDRL-FBT-Fire 4th Quarter 2020 Fire Brigade Drill (Announced) Shift #2 11/29/2020

drill

71111.06 Engineering EA-C-PAL-95- Palisades Nuclear Plant Analysis Continuation Sheet 3a

Evaluations 1526-01

EA-C-PAL-95- Palisades Nuclear Plant Analysis Continuation Sheet 4

26-01

Miscellaneous DBD-7.08 Plant Protection Against Flooding 6

Procedures SOP-17C Non-Radioactive Waste 13

Work Orders 52856590 01 Bus 1C; Inspection and Pump Out of Manholes 04/08/2020

71111.07A Corrective Action CR-PLP-2020- Unable to Isolate Service Water to VHX-27A 09/15/2020

Documents 03509

Work Orders 52860413 VHX027A Engineering Safeguards Room Cooling Coil 09/15/2020

71111.08P Corrective Action CR-PLP-2020- Ultrasonic Data Analysis of a Relevant Indication on 09/11/2020

Documents 03380 Penetration 34 on the Reactor Vessel Head

CR-PLP-2020- Ultrasonic Data Analysis of a Relevant Indication on 09/13/2020

03427 Penetration 17 on the Reactor Vessel Head

Miscellaneous 51-9318377-000 Palisades Steam Generator Condition Monitoring for 1R27 0

and Preliminary Operational Assessment for Cycle 28

PAL1R27 ETSS Examination Technique Specification Sheet 0

1. 1

PAL1R27 ETSS Examination Technique Specification Sheet 0

1. 2

PAL1R27 ETSS Examination Technique Specification Sheet 0

1. 3

PAL1R27 ETSS Examination Technique Specification Sheet 0

1. 4

PLP-RPT-18- 1R26 Palisades Steam Generator Degradation Assessment 1

00027

PLP-RPT-19- Palisades Steam Generator Condition Monitoring for 1R26 0

Inspection Type Designation Description or Title Revision or

Procedure Date

00020 and Final Operational Assessment for Cycle 27

Procedures 54-ISI-400-023 Multi-Frequency Eddy Current Examination of Tubing 23

54-ISI-400-023 NONDESTRUCTIVE EXAMINATION PROCEDURE 12/12/2018

Multi-Frequency Eddy Current Examination of SG Tubing

54-ISI-619-000 Automated Ultrasonic Examination of Open Tube RPV 07/30/2020

Closure Head Penetrations-Palisades Specific

CEP-NDE-0955 Visual Examination (VE) of Bare-Metal Surfaces 307

LMT-10-PAUT- Fully Encoded Phased Array Ultrasonic Examination of 3

007 Dissimilar Metal Piping Welds

SEP-BAC-PLP- Boric Acid Corrosion Control Program Engineering Nuclear 4

001 Programs Applicable Sites

71111.11Q Procedures SES-406 As Found Scenario 2

SOP-1C Primary Coolant System - Heatup 25

71111.12 Corrective Action CR-PLP-2020- The Main Feedwater System in Maintenance Rule Near 10/10/2020

Documents 04092 (a)(1)

CR-PLP-2020- 125V DC Bus Ground, Unexpectedly on DC Bus #1 10/16/2020

04185

CR-PLP-2020- DC Bus #1 10/18/2020

224

CR-PLP-2020- CRD-41 (Control Rod Drive Mechanism) Seal Leakoff 10/18/2020

232 Temperature Indication

CR-PLP-2020- Exceeded Maintenance Rule Performance Criteria on 10/30/2020

04455 PCS/PZR for Reliability Events

CR-PLP-2020- 125 Volt DC Bus Ground, #1 DC Bus 11/20/2020

04697

Engineering EC# 0000081574 ED-01 and ED-02: Evaluate Station Battery Remaining Life 02/21/2019

Changes Capacity Relative to Ambient Temperature

Miscellaneous Q1-2020 System RIA - Radiation Monitoring System 12/29/2020

Health Report

Q2-2020 System RIA - Radiation Monitoring System 12/29/2020

Health Report

Q2-2020 System EDC - 125V Vital DC Power 11/20/2020

Health Report

Q4-2020 System RIA - Radiation Monitoring System 12/29/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

Health Report

Procedures PLP-1-2020-0024 Risk Assessment, Station Battery Debris, Cracks 1

QE-35B ED-02 Battery Checks - Quarterly 18

Work Orders 5411188 01 72-15A ED-15 Charger Outlet Breaker Adjustable Trip 03/18/2020

Setting

71111.13 Procedures 4.11 Safety Function Determination Program 7

RE-134 Performance Test - Battery Charger No 2 (ED-16) 10

71111.15 Calculations 1R27 NaTB- Sodium Tetraborate Basket Weight Calculation Analysis 0

Analysis

Corrective Action CR-PLP-2020- While Installing Incore Detectors Under Work Order 09/18/2020

Documents 03608 5287985-28 Three Incore Detectors were Unable to be

Installed

CR-PLP-2020- Crack in the Outer Sheathing of the Cable for CET #32 09/29/2020

03882

CR-PLP-2020- Sodium Tetraborate Basket Weights 09/30/2020

03895

CR-PLP-2020- Breaker 52-187, Boric Acid Gravity Feed MO-2170 10/08/2020

04060

CR-PLP-2020- Engineering Safeguards Room Cooling System 10/09/2020

04076

CR-PLP-2020- Traveling Screen's Falk Drive a Severity Level 2 Oil Leak 11/04/2020

04505 was Noted

CR-PLP-2020- P-50B Lower (First) Seal Stage has a Lowering Trend 11/30/2020

04746

Engineering EC 88139 1R27 Results from RM-124 Sodium Tetraborate Basket 0

Changes Weights

EC-88128 Evaluation of Leakage Past E-50A Feed Reg Bypass Valve 0

CV-0735

Miscellaneous Adverse Primary Coolant Pump, P-50B, Rising Seal Pressure 11/04/2020

Condition

Monitoring and

Contingency Plan

Procedures RC-123 Sodium Tetraborate Decahydrate Buffering Tests 17

RM-124 Sodium Tetraborate Basket Weights 8

Inspection Type Designation Description or Title Revision or

Procedure Date

Work Orders 52871120 01 RC-123 - Sodium Tetraborate Decahydrate Buffering Test 09/08/2020

71111.18 Corrective Action CR-PLP-2020- Thermal Margin Monitor (TMM) PY-0102C Repeat 01/10/2020

Documents 00017 Functional Failure

CR-PLP-2020- B Thermal Margin Monitor (TMM) Screen has Gone Blank 03/31/2020

00716

CR-PLP-2020- TMM Channel 'A' Screen Degraded 03/09/2020

00752

CR-PLP-2020- Thermal Margin Monitor (TMM) PY-0102C Repeat 04/30/2020

01320 Functional Failure

CR-PLP-2020- PY-0102B, B Channel Thermal Margin Monitor/Flux Delta T 12/15/2020

04892 Power Comparator

CR-PLP-2020- Isolate MV-CD146, T-2 Cond Return from Boilers & B/D 12/16/2020

04898 Demins

CR-PLP-2020- EK-0604D Nuclear-OT Power Deviation/T-Inlet Off- 12/30/2020

04973 Normal/Calculator Trouble Channel B Unexpectedly

Engineering EC-84697 PY-0102D: TMM D Channel - Change Drawer CRT Video 12/03/2019

Changes Display Monitor to a New LCD Video Display Monitor

Procedures RI-23D Functional Testing of Thermal Margin Monitor - Channel D 02/14/2018

71111.19 Corrective Action CR-PLP-2020- Rod Deviation Alarms Were Received 08/30/2020

Documents 02795

CR-PLP-2020- Inspection and Testing of RSPT 40 Cable 10/14/2020

04151

CR-PLP-2020- Received Alarm EK-0918, PIP Trouble, Unexpectedly 10/16/2020

04172

CR-PLP-2020- Secondary Position Indication (SPI) on the PPC is Not 10/16/2020

04174 Indicating Properly

CR-PLP-2020- CRD-32, Control Rod Drive Mechanism, Primary Indication 10/16/2020

04178 Processor (PIP)

CR-PLP-2020- Control Rod Drive (CRD) #29 10/19/2020

248

CR-PLP-2020- Rod #2 Withdrew to 6" and Back to the Lower Electrical Limit 10/19/2020

275

CR-PLP-2020- Matrix Light on EC-12 Associated with CRD-17 was Not 10/20/2020

290 Illuminated When Expected

Inspection Type Designation Description or Title Revision or

Procedure Date

CR-PLP-2020- Found Green Corrosion on Right Positive Post of Cell #9 10/27/2020

04394

CR-PLP-2020- Door-142 (Turbine Building Access to the 1-C Switchgear 12/15/2020

04890 Room)

CR-PLP-2020- PMT for RV-0915, Component Cooling Surge Tank T-3 12/23/2020

04942 Relief

Procedures CVCO-4 Periodic Test Procedure - Charging Pumps 12

EN-MA-105 Control of Measuring and Test Equipment (MT&E) 17

MSI-I-16 Permanent Maintenance Procedure; Nonintrusive Diagnostic 12/15/2020

Check Valve Test Procedure

QO-15 Inservice Test Procedure - Component Cooling Water 12/15/2020

Pumps

RO-19 Control Rod Position Verification 10/17/2020

Work Orders 52876642 01 RO-19 - Control Rod Position Verification 10/14/2020

2890314 01 RV-0915, Component Cooling Surge Tank T-3 Relief 12/23/2020

2927113 01 CK-CC944, Nonintrusive Check Valve Test: I&C Support 12/15/2020

71111.20 Corrective Action CR-PLP-2020- Rod Deviation Alarms were Received 08/30/2020

Documents 02795

CR-PLP-2020- Unexpected Rising Trend on the "A" Steam Generator after 09/27/2020

03847 Preparing to Start Condensate P-2B

CR-PLP-2020- Liquid Penetrant (PT) Examination of the Reactor Vessel 10/06/2020

04026 CROM Penetration #34 Nozzle Repair Weld

CR-PLP-2020- 2 NPOs had to be Removed from Covered Work to Perform 10/12/2020

04104 Decontamination Activities in the Reactor Cavity

CR-PLP-2020- CCW hose for CRD Position 42 on the Reactor Head was 10/13/2020

04124 Found Frayed and Needs to be Replaced

CR-PLP-2020- CRD-45, Control Rod Drive Mechanism 10/14/2020

04137

CR-PLP-2020- CRD-28, Control Rod Drive Mechanism 10/16/2020

04180

CR-PLP-2020- Validation Confirmed CET 27 is Failed 10/17/2020

04195

CR-PLP-2020- Identified Exposed Insulation on "A" SIG Cold Leg 10/17/2020

204

Inspection Type Designation Description or Title Revision or

Procedure Date

CR-PLP-2020- P-80B AC Lift Pump Start Permissive was Erratic 10/17/2020

205

CR-PLP-2020- P-50B, Primary Coolant Pump, has Evidence of Prior Oil 10/17/2020

210 Leakage in its Drip Trays

CR-PLP-2020- CRD-41 (Control Rod Drive Mechanism) Seal Leakoff 10/18/2020

232 Temperature Indication

CR-PLP-2020- During Containment Walkdown Identified P-50D Primary 10/19/2020

243 Coolant Pump Motor Upper Oil Reservoir Line Leaking

Corrective Action CR-PLP-2020- NRC Walked Down Containment 10/20/2020

Documents 04285

Resulting from

Inspection

Procedures GOP-3 Mode 3 = 525°F to Mode 2 36

GOP-4 Mode 2 to Mode 1 10/21/2020

71111.22 Corrective Action CR-PLP-2020- CV-0847, SW Supply to Cont (MZ-12), the Open Stroke 10/04/2020

Documents 03987 Time was Outside of the Acceptable Stroke Time

CR-PLP-2020- P-8C Initial Vibrations Taken on the Pump Inboard Bearing 11/11/2020

04583 Were High Out of Specifications

CR-PLP-2020- P-8B, Steam Driven Auxiliary Feedwater Pump 11/13/2020

04613

CR-PLP-2020- QO-14C Performance 12/10/2020

04840

Procedures QO-14 Inservice Test Procedure - Service Water Pumps 11/18/2020

RO-145 Comprehensive Pump Test Procedure Auxiliary Feedwater 11/11/2020

Pumps P-8A, P-8B, and P-8C

RO-32 LLRT - Local Leak Rate Test 11/04/2020

Work Orders 00506694 01 P-7C; Replace Packing Shaft 11/18/2020

2878522 03 RO-145C -P-8C, AFW Comprehensive Pump Test 10/21/2020

71114.04 Miscellaneous 10 CFR 50.54(Q)(2) Screening - EI-1, Emergency 09/23/2019

Classification and Actions Revision 60

CFR 50.54(Q)(2) Screening - EI-1, Emergency 06/11/2020

Classification and Actions Revision 61

CFR 50.54(Q)(2) Screening - EI-2.2, Emergency Staff 10/07/2019

Augmentation Revision 22

Inspection Type Designation Description or Title Revision or

Procedure Date

CFR 50.54(Q)(2) Screening - EI-2.2, Emergency Staff 03/20/2020

Augmentation Revision 23

CFR 50.54(Q)(2) Screening - EI-3, Communications and 09/23/2019

Notifications Revision 36

CFR 50.54(Q)(2) Screening - EI-3, Communications and 01/23/2020

Notifications Revision 37

CFR 50.54(Q)(2) Screening - EI-4.1, Technical Support 10/21/2019

Center Activation Revision 26

CFR 50.54(Q)(2) Screening - EI-4.1, Technical Support 01/27/2020

Center Activation Revision 27

CFR 50.54(Q)(2) Screening - EI-4.2, Operations Support 10/21/2019

Center Activation Revision 27

CFR 50.54(Q)(2) Screening - EI-4.3, Emergency 01/19/2019

Operations Facility Activation Revision 30

CFR 50.54(Q)(2) Screening - EI-4.3, Emergency 05/14/2020

Operations Facility Activation Revision 31

CFR 50.54(Q)(2) Screening - EI-5.0, Reentry Revision 07/29/2019

CFR 50.54(Q)(2) Screening - EI-6.0, Rapid Dose 12/05/2019

Calculation Revision 19

CFR 50.54(Q)(2) Screening - EI-6.0, Rapid Dose 04/22/2020

Calculation Revision 20

CFR 50.54(Q)(2) Screening - EI-6.1, Release Rate 12/05/2019

Determination from Stack Gas Monitors Revision 10 CFR 50.54(Q)(2) Screening - EI-6.9, Automated Dose 04/22/2020

Assessment Program Revision 14

CFR 50.54(Q)(2) Screening - EI-6.13, Protective Action 12/17/2019

Recommendations for Offsite Populations Revision 26

CFR 50.54(Q)(2) Screening - EI-16.1, Maintenance of 11/26/2019

Emergency Equipment Revision 34

CFR 50.54(Q)(2) Screening - EN-EP-604, Emergency 06/08/2020

Classifications Revision 0

CFR 50.54(Q)(2) Screening - EN-EP-609 Emergency 02/18/2020

Operations Facility (EOF) Operations Revision 6

Inspection Type Designation Description or Title Revision or

Procedure Date

CFR 50.54(Q)(2) Screening - EN-EP-801, Emergency 10/29/2019

Response Organization Revision 17

CFR 50.54(Q)(3) Screening - PAL PWS, Public Warning 08/28/2019

System Operating Procedures Revision 23

CFR 50.54(Q)(3) Evaluation - PAL PWS, Public Warning 08/29/2019

System Operating Procedures Revision 23

CFR 50.54(Q)(3) Screening -PWS Design Report, Public 08/28/2019

Warning System Design Report Changes

CFR 50.54(Q)(3) Evaluation - PWS Design Report, 08/28/2019

Public Warning System Design Report Changes

CFR 50.54(Q)(3) Screening -SEP, Site Emergency Plan 09/18/2019

Revision 32

CFR 50.54(Q)(3) Evaluation -SEP, Site Emergency Plan 09/18/2019

Revision 32

Procedures EN-EP-305 Emergency Planning 10CFR50.54(q) Review Program 8

SEP Site Emergency Plan 31

SEP Site Emergency Plan 32

71124.08 Corrective Action CR-PLP-2020- EN-RW-102 Attachment 20 Incorrect Radiological Data 10/05/2020

Documents 03997

Miscellaneous Filter Characterization Report for F-57 Filters 06/05/2019

GEL Laboratories Part 61 Report for Primary Resin 07/13/2020

GEL Laboratories Part 61 Report for Filter 54A 11/25/2019

Shipping Records 2020-RW-003 Clean Radwaste F-57 Filters 02/11/2020

20-RW-004 Primary Purification Filter F54A 05/05/2020

20-RW-006 Primary Purification Resin 07/20/2020

71151 Miscellaneous NRC Performance Indicator Data; Mitigating Systems - 10/01/2019 -

Mitigating Systems Performance Indicator for Cooling Water 09/30/2020

Support Systems

NRC Performance Indicator Data; Mitigating Systems - 10/01/2019 -

Mitigating Systems Performance Index for Emergency AC 09/30/2020

Power Systems

71152 Corrective Action CR-PLP-2020- Ground Fault Experienced During Removal of Jumper 09/10/2020

Documents 3261

CR-PLP-2020- Control Room Entered AOP-36, "Loss of Component 09/10/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

262 Cooling Water"

Engineering 84321 K-7A, K-7B, Eliminate MFW PP Trip on Turbine Axial Thrust 0

Changes Position (Base EC)

Miscellaneous ACA Arc Fault Event 10/14/2020

DPRM/APRM Report 08/2020

Primary Coolant Pump Trends 12/16/2020

Procedures AOP-36 Loss of Component Cooling Water 2

2