IR 05000255/2021004

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Integrated Inspection Report 05000255/2021004 and Exercise of Enforcement Discretion
ML22031A283
Person / Time
Site: Palisades Entergy icon.png
Issue date: 02/08/2022
From: Billy Dickson
NRC/RGN-III/DRP/B2
To: Corbin D
Entergy Nuclear Operations
References
EA-21-159 IR 2021004
Download: ML22031A283 (27)


Text

SUBJECT:

PALISADES NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000255/2021004 AND EXERCISE OF ENFORCEMENT DISCRETION

Dear Mr. Corbin:

On December 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palisades Nuclear Plant. On January 19, 2022, 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 did not involve a violation of NRC requirements.

If you disagree with a cross-cutting aspect assignment or a finding not associated with a regulatory requirement 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 Nuclear Plant.

February 7, 2022 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:

DPR-20

Report Number:

05000255/2021004

Enterprise Identifier:

I-2021-004-0113

Licensee:

Entergy Nuclear Operations, Inc.

Facility:

Palisades Nuclear Plant

Location:

Covert, MI

Inspection Dates:

October 01, 2021 to December 31, 2021

Inspectors:

J. Cassidy, Senior Health Physicist

J. Corujo-Sandin, Senior Reactor Inspector

G. Hansen, Sr. Emergency Preparedness Inspector

J. Havertape, Reliability and Risk Analyst

P. Laflamme, Senior Resident Inspector

J. Mancuso, Resident Inspector, Donald C. Cook Nuclear Plant

C. St. Peters, Resident Inspector

R. Trelka, Reactor 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

Failure to Follow Preventative Maintenance Change Request Process Results in a Failure of Condensate Pump (P-2B) Oil Cooler and Subsequent Rapid Downpower Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green FIN 05000255/2021004-01 Open/Closed

[P.5] -

Operating Experience 71152 A finding of green significance was self-revealed on July 28, 2021, for the licensee's failure to follow their preventative maintenance change request (PMCR) process. Specifically, a preventative maintenance activity scope was changed without processing a PMCR, resulting in a failure to perform the preventative maintenance on the condensate pump (P-2B) oil cooler. As a result, a pin hole leak developed in the P-2B oil cooler leading to an oil/water mixture discharging from the P-2B motor's upper bearing housing sight glass vent, and the subsequent need to perform a rapid downpower of the reactor to secure P-2B.

Additional Tracking Items

Type Issue Number Title Report Section Status EDG EA-21-159 Failure to Comply with 10 CFR Part 37 71124.08 Closed

PLANT STATUS

The plant began the inspection period at full power and remained at or near full power for the entire inspection period.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, conducted routine reviews using IP 71152, Problem Identification and Resolution, observed risk significant activities, and completed on-site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

REACTOR SAFETY

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather Sample (IP Section 03.01) (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 November 4, 2020:

Service water system

Auxiliary feedwater (AFW) system

Impending Severe Weather Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated the adequacy of the overall preparations to protect risk significant systems from impending severe weather during a Geomagnetic Storm Watch on October 30, 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) Left train low pressure safety injection on October 6, 2021
(2) Right train high pressure safety injection on October 1, 2021
(3) Left train AFW on October 26, 2021
(4) Right train containment spray on December 4, 2021

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (8 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 1: Control Room/Elev. 625' and Fire Area 33: Technical Support Center/

Elev. 625' on October 1, 2021

(2) Fire Area 22: Turbine Lube Oil Room/ Elev. 590' on October 7, 2021
(3) Fire Area 29-31: Mechanical Equipment Room/ Elev. 629'-2" & 639' on October 13, 2021
(4) Fire Area 13G: Spent Fuel Pool Heat Exchanger Room/ Elev. 590' on October 16, 2021
(5) Fire Area 6 & 8: Diesel Generator 1-2 and Fuel Oil Day Tank Room/ Elev. 590' on November 13, 2021
(6) Fire Area 59: Auxiliary Feedwater Pump P-8D Room/ Elev. 590' on November 17, 2021
(7) Fire Area 15: Engineering Safeguards Panel and Stairway/ Elev. 570'-664' on December 2, 2021
(8) Fire Area 21: Electrical Equipment Room/ Elev. 607'-6" on December 13, 2021

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) Emergency Diesel Generator (EDG) rooms on October 18, 2021

71111.07T - Heat Sink Performance Heat Exchanger (Service Water Cooled) (IP Section 03.02)

The inspectors evaluated heat exchanger/sink performance on the following:

(1) Control Room Heating, Ventilation, and Air Conditioning (HVAC) Refrigerant Condensing Units (VC-10)
(2) Control Room HVAC Refrigerant Condensing Units (VC-11)

Ultimate Heat Sink (IP Section 03.04) (1 Sample)

(1) The Ultimate Heat Sink, Specifically Sections 03.04.d and 03.04.e were completed

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)

(1) The inspectors observed and evaluated licensed operator performance in the Control Room during a downpower to support QO-21C (P-8C AFW pump testing) on October 25, 2021.
(2) The inspectors observed and evaluated licensed operator performance in the Control Room during QO-1 SI Actuation Test (elevated risk evolution) - right train on November 30, 2021.

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

(1) The inspectors observed and evaluated PLSEG-LOR-21E-04, EOP 5.0, and PLSEG-LOR-21E-02, EP Static, on November 10, 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) Reactor protection system on October 27, 2021
(2) Primary coolant system on December 1, 2021

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (4 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) Emergent issues associated with EDG 1-2 monthly surveillance, on October 6, 2021
(2) Yellow risk due to left train of service water out of service for planned maintenance and testing, on October 14, 2021
(3) Emergent work activities associated with P-55A charging pump following speed oscillations, on November 12, 2021
(4) Emergent work activities on 1-2 EDG jacket water temperature switch, on December 1, 2021

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (3 Samples)

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

(1) Service water system evaluation on October 4, 2021
(2) Station Battery No. 1 and 2 system evaluation on December 13, 2021
(3) Pressurizer spray valve evaluation on December 15, 2021

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)-90291; T-2 Return Line Heat Exchanger Modification on December 6, 2021.

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (2 Samples)

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

(1) EDG 1-2 timed start following check valve replacement, on October 28, 2021
(2) CVCO-4 performed on the P-55A charging pump following flow drive replacement, on December 2, 2021

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) QO-15A, Inservice Test Procedure-Component Cooling Water Pump P-52A, on October 5, 2021
(2) QO-16C, Inservice test procedure-Containment Spray Pump P-54C, on October 13, 2021
(3) QO-1, SI Actuation Test (left train), on November 30, 2021

71114.04 - Emergency Action Level and Emergency Plan Changes

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

(1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes.

The licensee did not make any changes to the site's Emergency Action Level procedures or Emergency Plan during the period of this inspection (July 1, 2020 through June 30, 2021). The NRC inspectors independently reviewed the revisions of the site's Emergency Action Level procedures and Emergency Plan that were current for the inspection period to verify no changes were made.

This evaluation does not constitute NRC approval.

RADIATION SAFETY

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

Permanent Ventilation Systems (IP Section 03.01) (1 Sample)

The inspectors evaluated the configuration of the following permanently installed ventilation systems:

(1) Spent Fuel Pool Ventilation - Unit 1

71124.05 - Radiation Monitoring Instrumentation

Walkdowns and Observations (IP Section 03.01) (9 Samples)

The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:

(1) Portable Ion Chamber Dose Rate Instruments "Ready for Use" at the entrance to the radiologically controlled area
(2) Extendable Geiger-Mueller Dose Rate Instruments "Ready for Use" at the entrance to the radiologically controlled area
(3) Personnel Contamination Monitors used at the exit of the radiologically controlled area
(4) Small Article Contamination Monitor used at the exit of the radiologically controlled area
(5) Shepherd Model 89 Box Calibrator used to perform functional checks of portable dose rate instruments
(6) Portable Geiger-Mueller Frisker "Ready for Use" at the Main Access Facility
(7) Personnel Gamma Portal Monitor used to exit the Main Access Facility
(8) Personnel Contamination Monitors used at the exit of East Radwaste radiologically controlled area
(9) Personnel Gamma Portal Monitor used to exit East Radwaste radiologically controlled area

Calibration and Testing Program (IP Section 03.02) (13 Samples)

The inspectors evaluated the calibration and testing of the following radiation detection instruments:

(1) Model 3030 Scaler Serial Number 334592
(2) DMC-3000 Electronic Dosimeter Serial Number A168801
(3) Telepole Serial Number 6605-002
(4) RO-20 Serial Number 1445
(5) Shepherd Model 89 Box Calibrator Serial Number 91-1134
(6) Model 3 Frisker Instrument # 238945
(7) GEM-5 Monitor 1803-091
(8) ARGOS Monitor ID 1712-184
(9) PCM-2 ID 457
(10) SAM12 Serial Number 202
(11) RADECO Model HD-29A Air Sampler UTC No 17379
(12) Protean Model WPC-1050 Serial Number 11171115
(13) FASTSCAN Whole Body Counter Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (2 Samples)

The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:

(1) Unit 1, Liquid Radwaste Discharge Monitor, RIA-1049
(2) Unit 1, High Range Noble Gas Effluent Monitor, RIA-2327

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

Transportation

Radioactive Material Storage (IP Section 03.01)

(1) Inspectors evaluated the licensees performance in controlling, labeling, and securing radioactive materials.
(2) Inspectors evaluated the licensees performance in accounting and verification that sealed sources have been verified to be intact.

Radioactive Waste System Walkdown (IP Section 03.02) (1 Sample)

(1) Inspectors walked down accessible portions of the solid radioactive waste systems on 590' auxiliary building and evaluated system configuration and functionality.

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) October 1, 2020 - September 30, 2021

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

(1) October 1, 2020 - September 30, 2021 BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10) (1 Sample)
(1) October 2020 - September 2021

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

(1) October 2020 - September 2021 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) October 2020 - September 2021

71152 - Problem Identification and Resolution (PI&R)

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 during the period of July 1, 2021, to December 31, 2021.

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) Causal evaluation for 2B condensate pump oil cooler water intrusion and subsequent reactor power reduction as documented in CR-PLP-2021-01984 on November 29, 2021.

(2)1-2 EDG cylinder 7L crack and subsequent online maintenance and liner replacement causal evaluation as documented in CR-PLP-2021-02180 on December 16,

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

===71003 - Post-Approval Site Inspection for License Renewal The team conducted a partial Phase IV license renewal inspection (Section 02.02.d).

Specifically, with a focus on verifying the management of aging effects in accordance with the aging management program(s).

Post-Approval Site Inspection for License Renewal===

(1) The following aging management program was evaluated by the team:

Open Cycle Cooling Water Program

INSPECTION RESULTS

Enforcement Discretion Enforcement Action EA-21-159: Failure to Comply with 10 CFR Part 37 71124.08

Description:

On August 2, 2016, the licensee was issued NRC Inspection Report No. 05000255/2016407, which documented a licensee identified violation of 10 CFR Part 37, Physical Protection of Category 1 and Category 2, Quantities of Radioactive Material at Facilities with a 10 CFR Part 73, Physical Protection Program. The violation met the criteria for Enforcement Discretion as described in Enforcement Guidance Memorandum (EGM) 14-001, "Interim Guidance for Dispositioning 10 CFR Part 37 Violations with Respect to Large Components or Robust Structures Containing Category 1 or Category 2 Quantities of Material at Power Reactor Facilities Licensed Under 10 CFR Parts 50 and 52."

Subsequently, the inspectors re-evaluated this activity and found that while a violation of regulatory requirements continues to exist, the conditions remain within the criteria for enforcement discretion established within EGM 14-001.

Corrective Actions: As specified in EGM 14-001, the application of discretion is authorized until the underlying technical issue is dispositioned through rulemaking or other regulatory action. Additional corrective actions are not required.

Corrective Action References: Not Applicable.

Enforcement:

Violation: On August 2, 2016, a violation of 10 CFR Part 37 was documented in Palisades Inspection Report No.05000255/2016407. The inspectors determined that the previously identified violation remains.

Basis for Discretion: This violation met the criteria for Enforcement Discretion as described in Enforcement Guidance Memorandum (EGM) 14-001, "Interim Guidance for Dispositioning 10 CFR Part 37 Violations with Respect to Large Components or Robust Structures Containing Category 1 or Category 2 Quantities of Material at Power Reactor Facilities Licensed Under 10 CFR Parts 50 and 52."

Failure to Follow Preventative Maintenance Change Request Process Results in a Failure of Condensate Pump (P-2B) Oil Cooler and Subsequent Rapid Downpower Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green FIN 05000255/2021004-01 Open/Closed

[P.5] -

Operating Experience 71152 A finding of green significance was self-revealed on July 28, 2021, for the licensee's failure to follow their preventative maintenance change request (PMCR) process. Specifically, a preventative maintenance activity scope was changed without processing a PMCR, resulting in a failure to perform the preventative maintenance on the condensate pump (P-2B) oil cooler. As a result, a pin hole leak developed in the P-2B oil cooler leading to an oil/water mixture discharging from the P-2B motor's upper bearing housing sight glass vent, and the subsequent need to perform a rapid downpower of the reactor to secure P-2B.

Description:

On July 28, 2021, the control room received an unexpected alarm, EK-0162 (Condensate Pump P-2B High Temp or Overload), with the unit at full power. The licensee locally inspected condensate pump P-2B and found an oil/water mixture discharging from the motor's upper bearing housing sight glass vent. Shortly after discovering the oil/water mixture condition, the site entered Abnormal Operating Procedure (AOP) 7, "Rapid Downpower." The operators reduced power to approximately 25 percent and then secured pump P-2B. The licensee performed work order (WO) 565778. During the work, the licensee confirmed that the upper bearing oil cooler had developed a service water leak at one of the brass fittings used to connect to the service water inlet/outlet piping. The licensee cleaned and dried the upper bearing housing, then flushed the housing and bearing and installed a new bearing oil cooler. Pump P-2B was returned to service on July 29, 2021.

The licensee performed an apparent cause analysis (ACA). The ACA determined that sand entrained in the service water eroded the copper/brass cooler at a bend in the brass inlet/outlet connection, causing a pinhole leak at the brass fitting of the upper bearing oil cooler. The ACA identified that a preventative maintenance (PM) activity existed to replace the oil cooler periodically. In the ACA, the licensee noted their staff had deferred the PM activity several times, and the replacement did not occur as scheduled during the Fall 2018 refueling outage, 1R26. Instead, the PM activity was re-planned to use the 1R26 motor refurbishment work order to complete the oil cooler replacement. The licensee determined that their staff did not revise the 1R26 motor refurbishment work order to include oil cooler replacement. The ACA also noted incorrect interpretation of EN-WM-102, "Work Implementation and Closeout," and EN-DC-324, "Preventative Maintenance Program" by licensee staff. The wrong interpretation of EN-DC-324 resulted in the licensee staff changing the scope of the oil cooler replacement PM from replacement to cleaning and testing, which resulted in the oil cooler not being replaced. On the contrary, when the scope was changed, the licensee staff should have processed a PMCR per step 5.5.3 of EN-DC-324. The site also noted in the ACA that a previous leak in the P-2B motor upper oil cooler occurred on July 22, 2004, and also required a rapid downpower to remove the P-2B condensate pump.

The inspectors evaluated the licensee's emergent work, rapid downpower, post-maintenance testing, and ACA associated with this event. The inspectors determined the licensee failed to follow the PMCR process when changing the PMs scope, which resulted in the site failing to perform preventative maintenance.

Corrective Actions: The site wrote a condition report (CR) and performed an ACA. The licensee replaced the P-2B motor's upper bearing oil cooler. The site also added pre-outage refresher training to reinforce expectations. The site revised PMIDs and associated work orders to include a statement that the bearing oil cooler replacement is not to be delayed beyond the established PM due date. In addition, the licensee reinforced with staff that they cannot make changes to a work order without work order feedback or an approved PMCR.

Corrective Action References: CR-PLP-2021-1984

Performance Assessment:

Performance Deficiency: The licensee failed to follow fleet procedure EN-DC-324, "Preventative Maintenance Program," step 5.5.3. Specifically, the licensee changed the scope of the associated P-2B condensate pump oil cooler PM and failed to process a PMCR.

This led to the licensee crediting cleaning and testing by the motor vendor versus periodic replacement of the oil cooler, resulting in the P-2B oil cooler failing and the site performing a rapid downpower.

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. Specifically, the licensee changed the scope of the planned PM on the condensate pump P-2B oil cooler without processing a PMCR due to incorrect interpretation of EN-DC-324. The oil cooler eventually failed due to a pinhole leak from entrained sand, and the licensee had to perform a rapid downpower in order to take the P-2B condensate pump out of service.

Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors screened the finding against the Initiating Events screening questions in Exhibit 1 and answered "No" to the Transient Initiators question. This resulted in the finding screening to green.

Cross-Cutting Aspect: P.5 - Operating Experience: The organization systematically and effectively collects, evaluates, and implements relevant internal and external operating experience in a timely manner. Specifically, the licensee had previous operating experience with the same event happening in 2004. This operating experience, at the site, was not captured in the preventative maintenance activity to provide background as to why the PM activity existed.

Enforcement:

Inspectors did not identify a violation of regulatory requirements associated with this finding.

Observation: 1-2 EDG Cylinder 7L Crack Evaluation 71152 The inspectors reviewed the associated causal evaluation, "Why Staircase" analysis, equipment failure evaluation, the extent of condition, subsequent vendor analysis, and corrective actions taken for a crack in the liner of cylinder 7L on EDG 1-2 that the licensee discovered during a monthly surveillance test. Specifically, licensee personnel identified exhaust coming out of the associated crack on August 16, 2021, rendering the 1-2 EDG inoperable. After declaring the diesel generator inoperable, the licensee proceeded with a visual inspection of all cylinders on both diesel generators and subsequent liner replacement and verified that no additional cracks or exhaust leaks were present. In parallel, the inspectors performed an extent of condition walkdown of both EDGs, discussed the condition with operations, monitored liner replacement activities, and reviewed subsequent post-maintenance testing. The inspectors noted that the direct cause of the cylinder 7L liner crack was due to low-cycle fatigue. Specifically, the low-cycle fatigue resulted from preloading stress, thermal cycling, and non-uniform seating surface conditions going back to the original liner installation in 1996. The inspectors noted that both licensee and vendor review concluded the standards for seating surface conditions had been met at the time of original liner installation. Therefore, the inspectors determined that the identified crack was not within the licensees ability to foresee or prevent before identification during planned monthly testing on August 16, 2021. For corrective actions, the licensee successfully replaced the 7L liner and initiated measures to develop and implement a preventative maintenance strategy to ensure adequate seating surface conditions to lower fatigue stresses. The inspectors identified no issues of significance.

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 2021 through December 2021, 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 the steam dump control relay exceeding the vendor recommended service life, overheating, and rendering the atmospheric dump valves inoperable. The inspectors also observed and reviewed activities associated with other potential challenges to equipment reliability such as the station batteries having multiple cells with cracks, elevated control rod drive (CRD) temperatures, continued "B" primary coolant pump (PCP) seal degradation, and oil cooler replacement for the 2B condensate pump.

The inspectors noted that the licensee identified and monitored the station batteries cell cracks, including developing an adverse condition monitoring plan (ACMP) and performing more frequent inspections of the battery rooms. Also, the inspectors noted that the licensee monitored the increase in CRD 23 elevated temperatures, performed a weekly trend analysis of the seal pressures, and implemented ACMPs for the CRD temperature and for the PCP seal degradation. Regarding the oil cooler replacement, the licensee identified an unexpected alarm, recognized the potential cause, performed a rapid downpower to replace the oil cooler and reduce the potential for a transient to the plant, and completed an ACA to determine the cause of the oil cooler failure. Although these issues illustrated a challenge to equipment reliability, the inspectors reviewed the identified causes and 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 19, 2022, the inspectors presented the integrated inspection results to Mr. D. Corbin, Vice President, Operations, and other members of the licensee staff.

On December 8, 2021, the inspectors presented the radiation protection inspection results to Mr. D. Nestle, Radiation Protection Manager, and other members of the licensee staff.

On December 8, 2021, the inspectors presented the emergency plan and emergency action level changes review inspection results to Mr. D. Malone, Emergency Planning Manager, and other members of the licensee staff.

On December 14, 2021, the inspectors presented the triennial heat sink and license renewal phase 4 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

CR-PLP-2020-

03380

Framatone Indication Notification, Change in Material

Condition Reactor Head - Aging Example

09/11/2020

CR-PLP-2020-

04799

QI-5 Found Terminal Block Link #2 in Poor Condition - Aging

Example

2/03/2020

Corrective Action

Documents

CR-PLP-2021-

00733

PIC-1656 Failure - Aging Example

03/17/2021

Corrective Action

Documents

Resulting from

Inspection

CR-PLP-2021-

03130

SEP-RLP-PLP-001 Requirements are Difficult to Implement

2/10/2021

LR-AM R-OCC

Open Cycle Cooling Water System

Miscellaneous

LR-AMPBD-19-

OCCW

Open Cycle Cooling Water Program

NDE Reports

WDLC200316029

Coupon Analysis Report

03/25/2020

71003

Procedures

SEP-AMP-PLP-

2

Palisades Aging Management Program Assessment for

Failed or Degraded Equipment Program Section

Corrective Action

Documents

Resulting from

Inspection

CR-PLP-2021-

03171

NRC Identified: V-21F (Intake Structure Fresh Air Fan) is

Missing a Fastener on the Bottom Right Corner of the

Ventilator as Viewed from the Outside

2/15/2021

AOP-38

Acts of Nature

EN-CY-122

Diesel Fuel Oil Program

004

SOP-23,

Cold Weather Checklist

71111.01

Procedures

SOP-23,

Cold Weather Checklist - Electrical

Miscellaneous

DBD-2.03

Design Basis Document for Containment Spray System

SOP-12,

14

Auxiliary Feedwater System Checklist (Except K-8 Steam

Supply)

71111.04

Procedures

SOP-3,

18

Engineered Safeguards Administrative Control Verification

71111.05

Fire Plans

Pre-Fire Plan 1

Control Room, Elevation 625', Room 325 and Various

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Rooms

Pre-Fire Plan 13G

Spent Fuel Pool Heat Exchanger Room, Elevation 590',

Rooms 113, 113A, 114, & 115

Pre-Fire Plan 15

Auxiliary Building, Rooms 2, 16, and 121, Elevation 570' to

664'

Pre-Fire Plan 21

Electrical Equipment Room, Elevation 607'-6"; Room 725

Pre-Fire Plan 22

Turbine Lube Oil Room, Elevation 590', Room 132

Pre-Fire Plan 29,

30, & 31

Mechanical Equipment Rooms, Elevation 629'-2" & 639',

Various Rooms

Pre-Fire Plan 33

Technical Support Center, Elevation 625', Room 320A

Pre-Fire Plan 59

Auxiliary Feedwater Pump P-8D Room, Elevation 590'

Pre-Fire Plans 6

& 8

Diesel Generator 1-2 and Fuel Oil Day Tank Room,

Elevation 590', Rooms 116B & 147

Corrective Action

Documents

Resulting from

Inspection

CR-PLP-2021-

2879

Steam Leak in the 1-2 Diesel Generator Room on

Condensate Return Line in the Overhead

11/09/2021

13055

EA-C-PAL-95-1526-01: Internal Flooding Evaluation for

Plant Areas Outside Containment

29653

EA-C-PAL-95-1526-01: Internal Flooding Evaluation for

Plant Areas Outside Containment

43483

EA-C-PAL-95-1526-01: Internal Flooding Evaluation for

Plant Areas Outside Containment

43604

EA-C-PAL-95-1526-01: Internal Flooding Evaluation for

Plant Areas Outside Containment

43605

EA-C-PAL-95-1526-01: Internal Flooding Evaluation for

Plant Areas Outside Containment

Engineering

Changes

64658

EA-C-PAL-95-1526-01: Internal Flooding Evaluation for

Plant Areas Outside Containment

Miscellaneous

DBD-7.08

Design Basis Document for Plant Protection Against

Flooding

71111.06

Procedures

AOP-39

Internal Plant Flooding

2-M-001

Control Room Required Cooling Load

71111.07T

Calculations

RT-202 Basis

Palisades Nuclear Plant Technical Specification Surveillance 4/30/2009

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Procedure Basis Document for RT-202: Control Room

HVAC Heat Removal Capability

Corrective Action

Documents

CR-PLP-2015-

05765

UHS Triennial Inspection (2015) Minor Violation

11/19/2015

Appendix C,

Specification

2447/054-M-

91(Q)

Heat Exchanger Data Sheet

06/01/1983

B, MR

2447/054-M-

91(Q)

Design Specification for Water-Cooled Condensers

DBD-1.06

Design Basis Document for Control Room HVAC System

Fall 2020

Fall Cleaning Intake Structure Inspection:

11/12/2020

Spec M-91

Technical Specification for Condensing Units

Spring 2021

Spring Cleaning Intake Structure Inspection 2021

04/28/2021

SW Bay Fall 2015

Palisades Inspection Report for all Activities August 2015

through November 2015 UCC Project Number -

2-07-203.81

11/30/2015

SW Bay Fall 2018

2018 Mixing Basin 2018 Service Water Bay UCC Project

Number 02-07-203.101

11/17/2018

Miscellaneous

Vendor Manual

M0091-SH-0093

Operation, Maintenance, and Service Manual for

Condensing Units VC-10 & VC-11

DWO-1

Operator's Daily/Weekly Items Modes 1, 2, 3, and 4

2

EN-DC-184

NRC Generic Letter 89-13 Service Water Program

RO-216

Service Water Flow Verification

SEP-SW-PLP-

001

Raw Water Corrosion Program

SOP 15

Service Water System

Procedures

SOP-24

Ventilation and Air Conditioning System

00393862

P-7A Preservice Test (Vibration Data)

09/12/2020

00397938 01

BS-1319; Bolt That Holds Swing Washer is Broken Off -

MDM

04/14/2016

00443415 01

F-2A; Remove Cover & Inspect Basket Strainer

10/23/2019

Work Orders

51629058

Diver Inspection/Cleaning of Intake Bay (Fall)

2/10/2021

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

2774007

Divers to Clean/Inspect Service Water Pump Bay

11/15/2018

2788631

VC-10 Condenser Overhaul PM

04/17/2019

2803545

VC-11, Condenser Overhaul PM

05/09/2019

2834811

RT-202B, VC-10 CR HVAC "B" Train Heat Removal

Capability

08/28/2019

2836067

RT-202A, VC-11 CR HVAC "A" Train Heat Removal

Capability

01/30/2020

2871596

P-7B & P-7C Vibration Data RO-144

09/14/2020

2876336

Diver Inspection/Cleaning of Intake Bay (Spring)

05/04/2020

2896339

RT-202A, VC-11 CR HVAC "A" Train Heat Removal

Capability

08/06/2020

2898372

RT-202B, VC-10 CR HVAC "B" Train Heat Removal

Capability

07/29/2020

PLSEG-LOR-

21E-02

Emergency Planning Static

Miscellaneous

PLSEG-LOR-

21E-04

Emergency Operating Procedure 5.0

71111.11Q

Procedures

QO-21

Inservice Test Procedure Auxiliary Feedwater Pumps

CR-PLP-2018-

01523

PCP P-50A DC Oil Lift Pump did not Satisfy the Oil Pressure

Interlock

03/27/2018

CR-PLP-2019-

00130

PCS Leak Rates Since Start Up from the Refuel Outage

Have Been Elevated

01/09/2019

CR-PLP-2020-

04494

The Lower Stage of the Seal has a Lowering Trend

11/03/2020

CR-PLP-2021-

00080

Change to the P-50B, Primary Coolant Pump, Middle and

Upper Seal Pressures

01/13/2021

CR-PLP-2021-

2596

NI-6-RM10, Remote Power and VHPT Setpoint Meters, has

Lower than Expected Indication

10/09/2021

CR-PLP-2021-

2605

Primary Coolant Pumps

10/11/2021

CR-PLP-2021-

2642

Received EK-0926 Primary Coolant Pump P-50B Oil Level

Hi-Lo Unexpectedly

10/14/2021

71111.12

Corrective Action

Documents

CR-PLP-2021-

2644

PY-0102B, B Channel Thermal Margin Monitor

10/14/2021

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

CR-PLP-2021-

2662

The Display Screen for the 'B' Thermal Margin Monitor Went

Black for About 4 Seconds

10/17/2021

CR-PLP-2021-

2671

"B" TMM Screen Briefly Goes Blank and then Displays

Normal

10/18/2021

System Health Report PCS - Primary Coolant System

04/01/2019 -

06/30/2019

System Health Report PCS - Primary Coolant System

04/01/2020 -

06/30/2020

System Health Report PCS - Primary Coolant System

04/01/2021 -

06/30/2021

System Health Report PCS - Primary Coolant System

10/01/2019 -

2/31/2019

System Health Report PCS - Primary Coolant System

10/01/2020 -

2/31/2020

System Health Report RPS - Reactor Protection System

04/01/2019 -

06/30/2019

System Health Report RPS - Reactor Protection System

10/01/2019 -

2/31/2019

System Health Report RPS - Reactor Protection System

04/01/2020 -

06/30/2020

System Health Report RPS - Reactor Protection System

10/01/2020 -

2/31/2020

System Health Report RPS - Reactor Protection System

04/01/2021 -

06/30/2021

Maintenance Rule Performance Indicators Reactor

Protection System

2/08/2021

PLP-RPT-12-

00025,

Maintenance Rule Scoping Document Primary Coolant

System

Miscellaneous

PLP-RPT-12-

00026

Maintenance Rule Scoping Document Reactor Protection

System

EN-MA-156

Compression Fitting Installation, Disassembly, Inspection

and Reassembly

Procedures

EN-MA-158

Maintenance Configuration Control

03/26/2020

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

MI-43

Reactor Vessel Level Monitoring System Channel Check

03/26/2020

277252-01

P-50D Oil Level Transmitters

11/16/2018

28935-04

LT-0146B P/S Replacement

09/12/2020

Work Orders

541946-02

CV-1911; Ops PMT

2/24/2021

Procedures

EN-MW-104

On-Line Risk Assessment

565744-06

P-55A; Repair Sticking Poppet Valves (Contingency)

11/03/2021

568221-01

ASM-2B (K-6B); Replace CK-DE401, CK-DE423, RV-1485,

RV-1486

10/04/2021

568221-06

CK-DE401, Test Removed Check Valve

10/04/2021

568221-07

CK-DE421/CK-DE423 Test Removed Valve

10/04/2021

568221-08

RV-1485 Test Removed Valve

10/04/2021

568221-09

RV-1486 Test Removed Valve

10/04/2021

568221-13

RV-1486, Adjust Fuel Oil Relief Valve

10/04/2021

570079-01

P-55A; Adjust Crosshead Bearings

11/03/2021

571166-01

TS-1471 Replacement

11/30/2021

571166-02

TS-1471 Replacement (Prep Work)

11/29/2021

71111.13

Work Orders

571166-03

TS-1471 Replacement

2/01/2021

CR-PLP-2021-

2433

Service Water Leak Between Mechanical NPT Fitting and

Outlet of MV-SW602

09/21/2021

Corrective Action

Documents

CR-PLP-2021-

03174

CV-1059, Pressurizer Spray Valve from Loop 2A

2/15/2021

M-201

Piping & Instrument Diagram Primary Coolant System

Drawings

VEN-M-107

Stress Isometric Pressurizer Spray

91126

Operability Input for Service Water Leak Near Threaded

Fitting Downstream of MV-SW602

Engineering

Changes

EC-34881

Pressurizer Spray Valve CV-1057 and CV-1059 Revised

Packing Arrangement with Live Load Set

DBD-2.04

Primary Coolant System

DBD-2.11

Pressurizer Pressure Control

71111.15

Miscellaneous

ODM

Implementation

Plan Template

Packing Leakage on Pressurizer Spray Valve, CV-1059

2/02/2021

71111.18

Corrective Action

CR-PLP-2021-

Inboard Pump Bearing Oil Bubbler for P-52B Component

2/06/2021

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Documents

03087

Cooling Water Pump Nearly Empty

CR-PLP-2021-

2879

Steam Leak in the 1-2 Diesel Generator Room on

Condensate Return Line in the Overhead

11/09/2021

Corrective Action

Documents

Resulting from

Inspection

CR-PLP-2021-

03082

NRC Resident Found a Puddle of Water Surrounding E-924

2/06/2021

Drawings

M-208

Piping & Instrument Diagram Non-Critical Service Water

System

108

Emergent Issue

Update Template

Service Water Supply Line to T-2 Return Line Heat

Exchanger

11/11/2021

Miscellaneous

Failure Modes

and Effects

Worksheet

T-2 Return Line Heat Exchanger / EC-90291

09/20/2021

563541-26

E-924, Condensate Return Heat Exchanger Bypass Hex

10/15/2021

Work Orders

563541-43

E-924; Install New SWS Tie-In D/S of MV-SW939

11/18/2021

Procedures

CVCO-4

Periodic Test Procedure - Charging Pumps

71111.19

Work Orders

568221-10

ASM-2B (K-6B); Started Outside of Acceptable Start Time of

9.5

10/06/2021

2977575-01

QO-15A-P52A ISI Test Procedure, Component Cooling

Pump

09/16/2021

2978204-01

QO-16C-P54C, ISI Test Containment Spray Pump

09/27/2021

71111.22

Work Orders

2983287-01

QO-1 Safety Injection Actuation System Test

11/30/2021

EAL Basis

Emergency Action Level Technical Bases

EN-EP-305

Emergency Planning 10CFR50.54(q) Review Program

71114.04

Procedures

SEP

Palisades Nuclear Plant Site Emergency Plan

71124.03

Work Orders

2810325 01

RT-85C SFP Ventilation HEPA & Charcoal Testing

08/21/2019

21 Recalibration of The Mirion ABACOS -2000 Fastscan

Counting System at the Entergy - Palisades Power Plant

06/16/2021

21-B2.28-

CALDAT-00645

Model 3030 Scaler Calibration Serial Number 334592

01/27/2021

21-B2.28-

CALDAT-00747

DMC-3000 Calibration Sheet S/N A168801

01/28/2021

21-B2.28-

CALDAT-00920

WR Telepole S/N 6605-002 Calibration Data Sheet

2/05/2021

71124.05

Calibration

Records

21-B2.28-

RO-20 S/N 1445 Calibration Data Sheet

2/10/2021

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

CALDAT-00965

Inst Serial #91-

1134

130 Milli Curie Source Data Sheet

10/08/2020

Inst Serial# 91-

1134

400 Curie Source Data Sheet

10/08/2020

Instrument #

238945

Ludlum Model 3

07/28/2021

Monitor 1803-091

GEM-5 Calibration Data Sheet

06/08/2021

Monitor ID 1712-

184

ARGOS Calibration Data Sheet

07/19/2021

PCM-2 ID#457

PCM-2 Calibration Data Sheet

01/08/2021

SAM12 Serial

Number 202

SAM12 Calibration Data Sheet

2/25/2020

UTC No 17379

RADECO Model HD-29A Certificate of Calibration

2/11/2021

WPC-1050 Serial

Number

11171115

Protean Model WPC-1050 Calibration Coversheet

05/10/2021

Procedures

EN-RP-313

Operation and Calibration of the ARGOS-5AB Personnel

Contamination Monitor

Self-Assessments LO-PLPLO-2021-

00054

RP Radiation Monitoring Instrumentation Pre-NRC

Self-Assessment

08/12/2021

2907495 01

RR-9B Radwaste Discharge Monitor RIA-1049 Calibration

05/10/2021

Work Orders

2925326 01

RR-84C - Hi Range Noble Gas Effluent Mon RIA-2327 Cal

09/15/2021

Part 37 Security Plan for the Protection of Category 1 and

Category 2 Quantities of Radioactive Material

Training - 10 CFR Part 37 The Physical Protection of

Category 1 and Category 2 Quantities of Radioactive

Material

Miscellaneous

PLLP-RPCT-152-

10CFR37

Procedures

SIP 39

Protection of Category 1 and Category 2 Quantities of

Radioactive Material

71124.08

Self-Assessments LO-PLPLO-2021-

00031

10CFR Part 37 Transportation, Security Review, and

Self-Assessment

06/02/2021

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

2867088 01

Perform Annual Rad Source Inventory

01/15/2020

2916544 01

Perform Annual Rad Source Inventory

01/14/2021

Work Orders

2958379 01

Semiannual Sealed Source Leak Test

07/19/2021

Occupational Exposure Control Effectiveness Performance

Indicator Validation Package

Various

Reactor Coolant System Specific Activity Performance

Indicator Validation Package

Various

RETS/ODCM Radiological Effluent Occurrence Performance

Indicator Validation Package

Various

NRC Performance Indicators Mitigating Systems

Performance Indicator Cooling Water Support

(MS10 CWS-2)

10/01/2020 -

09/30/2021

71151

Miscellaneous

NRC Performance Indicators Mitigating Systems

Performance Indicator Emergency AC Power (EDG)

(MS06)

10/01/2020 -

09/30/2021

CR-PLP-2021-

01984

Received EK-0162, Condensate Pump P-2B High Temp or

Overload, Unexpectedly

07/28/2021

Corrective Action

Documents

CR-PLP-2021-

2180

Emergency Diesel Generator 1-2 Cylinder Liner 7L Cracked

10/15/2021

Apparent Cause Analysis Equipment Issues Over the

Cycle

Miscellaneous

Nuclear Independent Oversight Functional Area

Performance Report June 2021 - September 2021

EN-DC-324

Preventative Maintenance Program

EN-DC-324

Preventative Maintenance Program

EN-DC-324-DP

Decommissioning Plant Preventive Maintenance Program

008

Procedures

EN-WM-102

Work Implementation and Closeout

2436159-06

P-2B; Pump Motor (EMA-2205) Removal

10/10/2018

565778-01

EMA-2205/P-2B; Replace Upper Oil Cooler - E-908B

07/28/2021

565778-02

EMA-2205/P-2B; Stancion Installation/Grating Removal

07/28/2021

565778-04

Bench Test New Bearing Oil Cooler Coil

07/28/2021

565778-05

EMA-2205/P-2B; Instrument Interference Removal

07/28/2021

565778-06

EMA-2205/P2B; Drain Cooler Reservoir

07/28/2021

71152

Work Orders

565778-07

EMA-2205/P2B; Ops PMT

08/11/2021

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

565778-08

EMA-2205/P-2B; Instrument Interference Reinstall

07/29/2021

565778-10

EMA-2205/P-2B; Vibration Measurement

07/29/2021

565778-11

EMA-2205 (P-2B) Perform Megger Testing

07/29/2021