IR 05000255/2019004
| ML20028D909 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 01/28/2020 |
| From: | Billy Dickson NRC/RGN-III/DRP/B2 |
| To: | Corbin D Entergy Nuclear Operations |
| References | |
| IR 2019001, IR 2019004 | |
| Download: ML20028D909 (27) | |
Text
ary 28, 2020
SUBJECT:
PALISADES NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000255/2019004 AND 07200007/2019001
Dear Mr. Corbin:
On December 31, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palisades Nuclear Plant. On January 15, 2020, 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,
/RA/
Billy C. Dickson, Jr, Chief Branch 2 Division of Reactor Projects Docket No. 05000255; 07200007 License No. DPR-20
Enclosure:
As stated
Inspection Report
Docket Number: 05000255; 07200007 License Number: DPR-20 Report Number: 05000255/2019004; 07200007 Enterprise Identifier: I-2019-004-0054; I-2019-001-0115 Licensee: Entergy Nuclear Operations, Inc.
Facility: Palisades Nuclear Plant Location: Covert, Michigan Inspection Dates: October 01, 2019 to December 31, 2019 Inspectors: J. Cassidy, Senior Health Physicist J. Dalzell, Health Physicist R. Edwards, Senior Health Physicist E. Fernandez, Reactor Inspector G. Hansen, Sr. Emergency Preparedness Inspector P. Laflamme, Senior Resident Inspector V. Myers, Senior Health Physicist J. Winslow, 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 Type Issue Number Title Report Section Status LER 05000255/2018-003-01 LER 2018-003-01 for 71153 Closed Palisades Nuclear Plant,
Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations
PLANT STATUS
The plant began the inspection period at rated thermal power, 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 performed plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection Seasonal Extreme Weather Sample (IP Section 03.02)
- (1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the following systems during the week of November 11, 2019:
Auxiliary Feedwater (AFW) and Service Water
Impending Severe Weather Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated readiness for impending adverse weather conditions for a high wind warning on November 27, 2019
71111.04Q - Equipment Alignment Partial Walkdown Sample (IP Section 03.01)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Right Train Component Cooling Water (CCW) during maintenance and testing of P-52A on October 9, 2019
- (2) Left and Right Train Emergency Diesel Generators (EDGs) during P-7A Service Water Pump replacement on October 24 and 25, 2019
71111.05A - Fire Protection (Annual) Annual Inspection (IP Section 03.02)
- (1) The inspectors evaluated fire brigade performance during a drill on November 8, 2019
71111.05Q - Fire Protection Quarterly Inspection (IP Section 03.01)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Fire Area 23; Turbine Building - South Area on October 24, 2019
- (2) Fire Area 9; Screen House/Intake Structure during P-7A replacement on October 25, 2019
- (3) Fire Area 10; East Engineered Safeguards Room on November 29, 2019
71111.06 - Flood Protection Measures Inspection Activities - Internal Flooding (IP Section 02.02a.)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) 1D Switchgear Room, Cable Spreading Room, and Battery Rooms on December 30 and 31, 2019
71111.07A - Heat Sink Performance Annual Review (IP Section 02.01)
The inspectors evaluated readiness and performance of:
- (1) 1-2 EDG Jacket Water Heat Exchanger on December 23, 2019
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance Requalification Examination Results (IP Section 03.03)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification biennial written examinations and annual operating tests administered from February 18 through March 22, 2019.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Requalification Training/Examinations (IP Section 03.02)
- (1) The inspectors observed and evaluated Licensed Operator Requalification Training PLSEG-LOR-19E-01 on November 25, 2019
71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness Inspection (IP Section 02.01)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) Power supplies associated with the AFW actuation system during the week of December 16, 2019
- (2) Reactor Protection System during the week of December 16, 2019
71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Emergent troubleshooting and repairs following Source Range Neutron Flux Instrument Channel 1/3 Power Supply failure during the week of October 1, 2019
- (2) Elevated risk during scheduled 7A Service Water Pump replacement and testing during the week of October 21, 2019
- (3) Emergent troubleshooting and repairs following trip of VC-10 Control Room Heating, Ventilation, and Air Conditioning (HVAC) Condensing Unit and unplanned Limiting Condition for Operations (LCO) during the week of November 4, 2019
71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 02.02)
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Evaluation of NI-1/3A Failure during the week of October 7, 2019
- (2) 1-1 EDG Turbocharger Operability as documented in CR-PLP-2019-004060 on October 17, 2019
- (3) Evaluation of acceptability for carbon steel nuts on P-7A Service Water Pump as documented in CR-PLP-2019-04275 on October 24, 2019.
- (4) Evaluation of loose shim packs on discharge head to floor connection of P-7A Service Water Pump as documented in CR-PLP-2019-04832 on December 9, 2019
71111.18 - Plant Modifications Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Engineering Change (EC) 83228, Removal of Service Water Pump Lateral Restraints on November 22, 2019
71111.19 - Post-Maintenance Testing Post-Maintenance Test Sample (IP Section 03.01)
The inspectors evaluated the following post maintenance tests:
- (1) RI-99 after replacement of Source Range Neutron Flux Power Supply on October 2, 2019
- (2) MO-7A1 following A1 starting air pressure controller (PCV-1479) on October 7, 2019
- (3) QO-19 after P-66B motor testing on October 16, 2019
- (4) QO-14 after P-7A motor replacement on October 24, 2019
71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Surveillance Tests (other) (IP Section 03.01)
- (1) QO-21C; P-8C AFW System Test on October 30, 2019
- (2) QO-16B; P-54B Containment Spray Test on November 5, 2019
- (3) RT-71M; Class 2 Inservice Test for Safety Injection and Refueling Water Tank on November 20, 2019
71114.04 - Emergency Action Level and Emergency Plan Changes Inspection Review (IP Section 02.01-02.03)
- (1) The inspector completed the evaluation of submitted Emergency Action Level and Emergency Plan changes on November 25, 2019. This evaluation does not constitute NRC approval.
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls Radiological Hazard Assessment (IP Section 02.01)
The inspectors evaluated radiological hazards assessments and controls.
- (1) The inspectors reviewed the following:
Radiological Surveys
- 649' Spent Fuel Pool Area
- East Safeguards Area
- 590' Primary System Drain Tank Pump Room Risk Significant Radiological Work Activities
- Dry Fuel Storage Campaign - Loading Cask
- Offline Electrical Motor Testing
- Semi-Annual Locked High Radiation Area Verification Air Sample Survey Records
- PLP-AS-100819-0689
- PLP-AS-101119-0707
- PLP-AS-101119-0708
Instructions to Workers (IP Section 02.02) (1 Sample)
The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas.
- (1) The inspectors reviewed the following:
Radiation Work Packages
- 20190107 - Decontamination and Housekeeping Activities in Locked High Radiation/High Radiation Areas/High Contamination Areas
- 20190209 - Activities Requiring Access to Locked High Radiation Areas
- 20190240 - Dry Fuel Storage Campaign - Preparation, Loading, and Demobilization Electronic Alarming Dosimeter Alarms
- Error 70111 11/25/2018 04:55 Labeling of Containers
- Hose Storage Box 649' Spent Fuel Pool
- Areva Camera Equipment 649' Spent Fuel Pool
- Crane Control Tool Box 649' Spent Fuel Pool
- Contaminated Drum 625' Track Alley
- High Efficiency Particulate Air Vacuum Cleaners 625' Storage Area Contamination and Radioactive Material Control (IP Section 02.03) (1 Sample)
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.
- (1) The inspectors verified the following sealed sources are accounted for and are intact:
- CE-9848
- 87-CS-S-18 Radiological Hazards Control and Work Coverage (IP Section 02.04) (1 Sample)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.
- (1) The inspectors also reviewed the following radiological work package for areas with airborne radioactivity:
- No work packages were available for review during this inspection.
High Radiation Area and Very High Radiation Area Controls (IP Section 02.05) (1 Sample)
- (1) The inspectors evaluated risk-significant high radiation area and very high radiation area controls.
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 02.06) (1 Sample)
- (1) The inspectors evaluated radiation worker performance and radiation protection technician proficiency.
71124.02 - Occupational ALARA Planning and Controls Radiological Work Planning (IP Section 02.01)
The inspectors evaluated the licensees radiological work planning.
- (1) The inspectors reviewed the following activities:
- 2018-0434; Reassembly of the Reactor Head and Associated Work Activities
- 2018-0444; Removal/Installation of Control Rod Drive Seal Housing Packages and Removal/Installation of Drive Motors
- 2018-0450; Under Head Repair
- 2018-0454; Steam Generator Primary Side Activities Verification of Dose Estimates and Exposure Tracking Systems (IP Section 02.02) (1 Sample)
The inspectors evaluated dose estimates and exposure tracking.
- (1) The inspectors reviewed the following as low as reasonably achievable planning documents:
- 2018-0434; Reassembly of the Reactor Head and Associated Work Activities
- 2018-0444; Removal/Installation of Control Rod Drive Seal Housing Packages and Removal/Installation of Drive Motors
- 2018-0450; Under Head Repair
- 2018-0454; Steam Generator Primary Side Activities
71124.05 - Radiation Monitoring Instrumentation Calibration and Testing Program (IP Section 02.02)
The inspectors evaluated the calibration and testing program implementation.
- (1) The inspectors evaluated the calibration program for the containment high range radiation monitors. These activities supplement those in inspection report
===05000255/2019002 and constitute a complete sample.
71124.08 - Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation Radioactive Material Storage (IP Section 02.01)
The inspectors evaluated radioactive material storage.
- (1) The inspectors toured the following areas:
- East Radioactive Waste Building
- South Storage Building
- Refueling Outage Materials Pole Barn The inspectors performed a container check (e.g., swelling, leakage and deformation)on the following containers:
- 4 Boxes outside East Radioactive Waste Building
- 3 Boxes inside East Radioactive Waste Building
- 2 Boxes Inside South Storage Building
- 3 Boxes Inside Refueling Outage Materials Pole Barn
- 1 High Integrity Container Outside the Steam Generator Blowdown Resin Vessels Radioactive Waste System Walkdown (IP Section 02.02) ===
The inspectors evaluated the following radioactive waste processing systems [and processes] during plant walkdowns:
- (1) Liquid or Solid Radioactive Waste Processing Systems
- Advanced Liquid Processing System
- Steam Generator Secondary Blowdown Resins
- M-18 Sludge and Waste Oil Collection Radioactive Waste Resin and/or Sludge Discharges Processes
- Advanced Liquid Processing System
- Steam Generator Secondary Blowdown Resins Waste Characterization and Classification (IP Section 02.03) (1 Sample)
The inspectors evaluated the radioactive waste characterization and classification for the following waste streams:
(1)
- Dry Active Waste
- Advanced Liquid Processing System Resins
- Tank 100 Resins
Shipment Preparation (IP Section 02.04) (1 Sample)
The inspectors evaluated the following radioactive material shipment preparation processes:
- (1) The inspectors evaluated training and qualification records for selected individuals due to limited observation of the radioactive material shipment preparation process.
Shipping Records (IP Section 02.05) (1 Sample)
The inspectors evaluated the following non-excepted package shipment records:
(1)
- 2017-RW-017
- 2018-RW-004
- 2018-RW-007
- 2018-RW-011
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, 2018 - September 30, 2019)
MS10: Cooling Water Support Systems (IP Section 02.09) (1 Sample)
- (1) Unit 1 (October 1, 2018 - September 30, 2019)
71152 - Problem Identification and Resolution Semiannual Trend Review (IP Section 02.02)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in critical component failures that might be indicative of a more significant safety issue.
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) Human performance issues associated with the failure to block the main steam isolation valve (MSIV) closure interlock within the required band on July 28, 2019, as documented in CR-PLP-2019-02920 and the unplanned transfer of water to the safety injection and refueling water tank (SIRWT) on September 4, 2019, as documented in CR-PLP-2019-03474.
71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000255/2018-003-01, Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations (ADAMS accession: ML19210D347)
The inspectors reviewed the updated LER submittal. The previous LER submittal was reviewed in Inspection Report 05000255/2019002 Sections 71111.08 and
===71153. The inspectors concluded that no additional violations of NRC requirements occurred.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 60855.1 - Operation of an Independent Spent Fuel Storage Installation at Operating Plants Operation of an Independent Spent Fuel Storage Installation at Operating Plants ===
- (1) The inspectors evaluated the licensees independent spent fuel storage installation cask loading activities on September 30th through October 4th. Specifically, the inspectors observed the following activities;
- Installation of the transfer cask (HI-TRAC) lid
- Alternate cooling operations
- Hydrostatic testing and non-destructive weld evaluations
- Canister processing including bulk water removal (blowdown) and forced helium dehydration
- Vent and drain port cover welding and non-destructive weld evaluations
- Helium leak testing
- Radiological field surveys The inspectors performed walkdowns of the East and North ISFSI pads, including independent radiation surveys, and walkdowns of the ISFSI haul path and vertical cask transporter (VCT).
The inspectors evaluated the following:
- Spent fuel selection for the three casks for this loading campaign
- Selected corrective action program action requests
- Selected 72.48 screenings and evaluations
INSPECTION RESULTS
Assessment 71152 The inspectors reviewed evaluations associated with two human performance errors documented in the corrective action program (CAP), including completed and planned corrective actions and effectiveness reviews. On July 28, 2019, during plant cooldown from Mode 3 to Mode 5, the licensee failed to block the main steam isolation valve (MSIV) closure interlock within the required band per procedure. No valve actuations occurred as a result of the failure to block the interlock because previous operator actions closed both MSIVs. The licensee's investigation of the issue revealed that Operations personnel were aware of the procedure step, but prioritized a required step to block the safety injection signal (SIS) prior to blocking the MSIV closure interlock because they believed there was enough time to block SIS then block the MSIV closure interlock. Following completion of blocking the SIS, the operators identified that steam generator pressures were below the required band for blocking the MSIV closure interlock. The operators verified system logic and blocked the MSIV closure interlock.
On September 4, 2019, the licensee identified that a valve was not closed as required per procedure SOP-27, "Fuel Pool System" during a change in system configuration. This resulted in the unplanned transfer of water from the spent fuel pool to the safety injection and refueling water tank (SIRWT). The operators verified all valve positions associated with the evolution and identified that MV-SFP127, spent fuel pool (SFP) demineralizer T-50 outlet to SIRWT, was partially open when it should have been closed. The operators then closed MV-SFP127 to establish the appropriate system configuration. The inspectors reviewed the licensee's final adverse condition analysis, and discussed the results of the analysis with the licensee.
Additional corrective actions from the evaluations included communicating lessons learned from these events with all operating crews. The inspectors determined that the corrective actions were appropriate and timely based on the safety significance of the issues.
Minor Violation 71152 Minor Violation: The inspectors reviewed CR-PLP-2019-03474 associated with the unplanned transfer of water to the SIRWT. The licensee identified that standard operating procedure SOP-27, "Fuel Pool System," was not implemented as written. Specifically, on September 4, 2019, operators did not implement step 7.3.4(e)(2), which states to "close and lock MV-SFP127," as written. This resulted in the inadvertent transfer of water from the spent fuel pool to the SIRWT. Standard operating procedure SOP-27 provides instructions for operation of the spent fuel pool system as discussed in Regulatory Guide 1.33, Revision 2, Appendix A, Section 3.h. The inspectors identified this as a minor violation of Technical Specification (TS) 5.4.1.a. Licensee staff documented this issue in their CAP as CR-PLP-2019-03474.
Screening: The inspectors determined the performance deficiency was minor. Consistent with the guidance in IMC 0612, "Power Reactor Inspection Reports," Appendix B, "Issue Screening," the inspectors determined that the performance deficiency was not a finding of more than minor significance based on answering 'No' to all of the more-than-minor screening questions. The inspectors also reviewed the examples of minor issues in IMC 0612, Appendix E, "Examples of Minor Issues," and determined that this issue was most closely related to Example 4.b in that that this was a procedural error that had no safety consequences.
Enforcement:
This failure to comply with TS 5.4.1.a constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
Minor Violation 71152 Minor Violation: The inspectors reviewed CR-PLP-2019-02920 associated with the failure to block the MSIV closure interlock in the required band. The licensee identified that general operating procedure GOP-9, "Mode 3 > 525F to Mode 4 or Mode 5," was not implemented as written. Specifically, on July 28, 2019, operators did not implement step 3.7, which states "When 3 of 4 associated Steam Generator pressure sigmas indicate between 510 and 550 psia and the indicator is between alarm flags, then depress the associated pushbutton to bypass MSIV closure: HS/LPE-50A, bypass of MSIV closure pushbutton; and HS/LPE-50B, bypass of MSIV closure pushbutton," as written when they did not depress HS/LPE-50A and HS/LPE-50B when 3 of 4 associated Steam Generator pressure sigmas indicated between 510 and 550 psia. General operating procedure GOP-9 provides instructions for general plant operating procedures from hot standby to cold shutdown as discussed in Regulatory Guide 1.33, Revision 2, Appendix A, Section 2.j. The inspectors identified this as a minor violation of TS 5.4.1.a. This issue was documented in the licensee's CAP as CR-PLP-2019-02920.
Screening: The inspectors determined the performance deficiency was minor. Consistent with the guidance in Inspection Manual Chapter (IMC) 0612, "Power Reactor Inspection Reports," Appendix B, "Issue Screening," the inspectors determined that the performance deficiency was not a finding of more than minor significance based on answering 'No' to all of the more-than-minor screening questions. The inspectors also reviewed the examples of minor issues in IMC 0612, Appendix E, "Examples of Minor Issues," and determined that this issue was most closely related to Example 4.b in that that this was a procedural error that had no safety consequences.
Enforcement:
This failure to comply with TS 5.4.1.a constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.
Observation: Semi-Annual Trend Review 71152 The inspectors review focused on critical component failures/ degradation and subsequent challenges to online and equipment reliability, but also considered the results of daily inspector CAP item screening and licensee trending efforts. The inspectors review nominally considered the 6-month period of July 2019 through December 2019, although some examples expanded beyond those dates when warranted by the scope of the trend.
The inspectors reviewed condition reports, trend reports, maintenance rule evaluations, and causal evaluations 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 thermal margin monitor (TMM) channel C and D screen failures and subsequent inoperabilities, a failed source range power supply to NI Channels 1 & 3 and resultant inoperability, the loss of V-49A, CRDM cooling fan (1 of 2) resulting in slightly higher CRDM seal temperatures, multiple momentary losses of group 2 pressurizer backup heaters, and CRDM #14 & #23 seal degradation coupled with the digital electro-hydraulic system power supply failure and resultant maintenance outage.
For the latter two instances, the inspectors noted that the licensee identified, monitored, and then repaired both equipment issues during a planned maintenance outage July 27-31, 2019.
Regarding the multiple TMM screen failures and subsequent screen replacement, the inspectors noted that the licensee identified their lack of sufficient long-term planning to ensure TMM reliability as a contributing cause. For corrective action, the licensee plans to install new LCD replacement screens of higher quality. The licensee concluded that this will also address the reliability concerns. Although these issues illustrated a challenge to online and 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 15, 2020, the inspectors presented the integrated inspection results to Mr. D. Corbin, Vice President, Operations, and other members of the licensee staff.
- On October 4, 2019, the inspectors presented the Radiation Protection Program inspection results to Mr. D. Corbin, Vice President, Operations, and other members of the licensee staff.
- On October 21, 2019, the inspectors presented the Independent Spent Fuel Storage Installation inspection results to Mr. D. Lucy, Acting Site Vice President and other members of the licensee staff.
- On November 15, 2019, the inspectors presented the Radiation Protection Program inspection results to Mr. D. Corbin, Vice President, Operations, and other members of the licensee staff.
- On November 25, 2019, the inspectors presented the Emergency Action Level and Emergency Plan Changes inspection results to Mr. D. Malone and other members of the licensee staff.
- On December 17, 2019, the inspectors presented the Licensed Operator Requalification program annual examination results review inspection results to Mr. F. Korfias, Operations Exams Superintendent and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
60855.1 ALARA Plans EN-RP-105 Radiological Work Permits 18
Corrective Action Review of Selected Corrective Action Reports Since
Documents January 2017
CR-PLP-2016- HI-STORM FW Combustible Controls 11/16/2016
05475
Engineering EC-71123 Perform Modification to Change the East Trolley Limit Switch 0
Changes on L-3 per CR 2016-4562
Miscellaneous Certificate of Compliance No. 1032, Amendment No. 1 1
Final Safety Analysis Report on the HI-STORM FW MPC 4
Storage System
Selected 10 CFR 72.48 and 50.59 ISFSI Related Screenings
and Evaluations Since January 2017
Response to Palisades NRC Inspection Question on 10/02/2019
HI-TRAC Lift Bracket Bolt Inspection per HSP-366
Certificates of Conformance for Purchase Order 107236 08/12/2015
DOC-103-007R2 Leased HI-TRAC VW for Use at Palisades (Entergy) 09/26/2019
Documentation Package
DOC-104-107- Leased MPC-37 Lift Bracket for HI-STORM FW 06/25/2019
016R1 Documentation Package
DOC-104-209- Leased MPC-37 Lift Cleat Documentation Package 06/25/2019
018R1
DOC-104-702- Leased HI-TRAC VW Lift Yoke to Palisades Documentation 06/25/2019
23R1 Package
DOC-104-731- Leased MPC Lid Lift Adapter and MPC Lid Lift Rigging 06/25/2019
019R1 Documentation Package
DOC-2251- Lower Fuel Shims for Palisades Nuclear Plant 08/09/2019
004R1 Documentation Package
DTF-3005-015B Palisades Training Records 09/24/2019
EN-DC-223 MPC Loading Plan for MPC 123, 124 and 125 Revision 4
PROC No. MPC-37 Fuel Verification 10/01/2019
FSHO-17A
Inspection Type Designation Description or Title Revision or
Procedure Date
Report No. PLP Palisades 10 CFR 72.212 Evaluation Report 09/09/2019
21032
NDE Reports Report No. Report of Visual Non-Destructive Examination 10/04/2010
915741-123-01
WO 52844949-01 Annual Crane Liquid Penetrant Examination 08/08/2019
Procedures AT-36 ISFSI Pad Monitoring Program 5
AT-9 Examination of Ventilated Concrete Cask Assembly Exterior 7
GQP - 9.2 High Temperature Liquid Penetrant Examination and 10
Acceptance Standards for Welds, Base Materials and
Cladding (50° - 350°F)
GQP - 9.6 Visual Examination of Welds 18
Procedure No. HI-STORM FW Dry Fuel Loading Operations - MPC Loading 5
FHS-M-41B
Procedure No. HI-STORM FW Dry Fuel Loading Operations - MPC Sealing 8
FHS-M-41C and Drying
Procedure No. HI-STORM FW Dry Fuel Loading Operations - MPC Transfer 9
FHS-M041D to HI-STORM
Radiation Periodic Radiological Surveys Performed Since
Surveys January 2017
Self-Assessments 2019 Readiness Assessment 09/05/2019
QA-20-2018-PLP- Audit Report: Independent Spent Fuel Storage Installation 07/08/2019
Work Orders HSP-169 HI-STORM Offloading and Preparation for Site Fabrication 36
Completion
WO 00517524-04 Limits on Crane are Not Working Properly - Investigate 07/25/2019
WO 52832037 AT-9 Dry Fuel Storage Cask Exterior Inspection 06/04/2019
WO 52832038 AT-36 ISFSI Pad Monitoring Program 07/25/2019
71111.01 Corrective Action CR-PLP-2019- NRC Identified Gaps in Insulation 11/21/2019
Documents 04653
Resulting from CR-PLP-2019- NRC Resident Identified a Cable/Extension Cord Hanging 11/27/2019
Inspection 04723 Over the Edge of the Roof on the North Side of the Turbine
Building
CR-PLP-2019- Unsecure Items Identified by the NRC 12/06/2019
04807
Inspection Type Designation Description or Title Revision or
Procedure Date
Miscellaneous Certificate of Analysis for T-10A 07/29/2019
Site Certification Letter for Winter Readiness 2019/2020
2019-2020 Winter Weather Contingency Plan 6
Procedures AOP-38 Acts of Nature 18
EN-CY-122 Diesel Fuel Oil Program 2
EN-FAP-EP-010 Attachment 7.14, Severe Weather Missile Hazard Reduction 7
Guidance
SOP-15 Service Water System 69
SOP-23 Plant Heating System 62
Work Orders WO 52848891 Perform Cold Weather Checksheets 10/23/2019
71111.04Q Corrective Action CR-PLP-2019- A Small Puddle of Fuel Oil was Noticed on the Floor Below 03/13/2019
Documents 01047 MV-FO705, P-18A/B Discharge to FO Day Tank T-40
CR-PLP-2019- HP Air Compressor in West Safeguards was Found to Have 07/19/2019
2813 a Minor Leak
CR-PLP-2019- MV-CC942, Component Cooling Water (CCW) P-52B 10/10/2019
04084 Discharge, has Evidence of Past Leakage on the East Side
of the Upper Flange
CR-PLP-2019- Observed Roof Leak of ~60-80 Drops per Minute on West 10/30/2019
04344 Side of 625' Elevation of Turbine Deck
CR-PLP-2019- CK-FW743, Auxiliary Feedwater Pump P-8B has a Body to 10/31/2019
04369 Bonnet Leak of 5 Drops per Minute
Corrective Action CR-PLP-2019- NRC Identified a Large Amount of Carbon Build Up on the 10/11/2019
Documents 04101 Southwest Portion of the Turbocharger
Resulting from
Inspection
Drawings M-214, Sheet 1 Piping & Instrument Diagram, Lube Oil, Fuel Oil, & Diesel 82
Generator Systems
Miscellaneous DBD-1.03 Design Basis Document for Auxiliary Feedwater System 10
Procedures SOP-12, Auxiliary Feedwater System Checklist 81
14
SOP-22 Emergency Diesel Generators 77
71111.05A Procedures EN-TQ-125 PLDRL-FBT-FIREDRILL (19-018) 11/08/2019
EN-TQ-125, Fire Drill Report 11/15/2019
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.05Q Fire Plans Pre Fire Plan East Engineered Safeguards Room/ Elevation 570' 5
Area 10
Pre Fire Plan Turbine Building - South / Elevation 590' 5
Area 23
Pre Fire Plan Screen House / Intake Structure / Elevation 590' 5
Area 9
Procedures EN-DC-161 Control of Combustibles 20
71111.06 Calculations EA-C-PAL-95- Internal Flooding Evaluation for Plant Areas Outside 3a
26-01 Contaiment
Corrective Action CR-PLP-2019- PMID 50083994-02 May Not be Effective 12/13/2019
Documents 04899
CR-PLP-2019- Two of Three Drains in Cable Spreading are Plugged 12/17/2019
04945
71111.07A Corrective Action CR-PLP-2019- Eddy Current Testing of the E-31B "EDG 1-2 Lube Oil 03/19/2019
Documents 01138 Cooler"
Procedures EPS-M-14A Diesel Generator Every Cycle Maintenance 03/18/2019
SEP-HX-PLP-001 Supplemental HX Visual Inspection Checklist - Jacket Water 03/18/2019
Cooler
Work Orders 52771367-01 K-6B 1-2 D/G 24 Month PM 03/18/2019
71111.11A Miscellaneous Palisades Annual Licensed Operator Requalification 3/29/2019
Summary Results for 2019
71111.11Q Corrective Action CR-PLP-2019- The CRT Screen for PY-0102A 'A' Channel Thermal Margin 10/21/2019
Documents 04224 Monitor is Growing Dim
CR-PLP-2019- During Training, Instructor Identified that the InForm 11/07/2019
04476 Program was Configured to the "Palisades" Jurisdiction
71111.12 Corrective Action CR-PLP-2018- EC-187D, AFAS Sensor Channel Cabinet, has No 12 Volt 11/02/2018
Documents 05433 DC Power
CR-PLP-2019- Received EK-0137, Auxilary Feedwater AFAS-FOGG 03/23/2019
213 Subsystem Trip
CR-PLP-2019- P/S-0712 from CR-PLP-2018-05433 was Not Sent to the 03/25/2019
222 Vendor for Failure Analysis
CR-PLP-2019- Maintenance Rule (a)(1) Action Plan, Thermal Margin 12/04/2019
03549 Monitor (TMM) Displays
CR-PLP-2019- PY-0102C: Thermal Margin Monitor Channel 'C' Display has 09/14/2019
Inspection Type Designation Description or Title Revision or
Procedure Date
03687 Dimmed in is now Unreadable
CR-PLP-2019- Two Maintenance Rule Repeat Functional Failures 10/07/2019
04016 Associated with the Thermal Margin Monitors (TMM)
CR-PLP-2019- Documented Failures of TMM Circuit Cards 11/14/2019
04540
CR-PLP-2019- NI-07 Power Range Instrumentation 11/19/2019
04603
CR-PLP-2019- PY-0102C: Thermal Margin Monitor Channel 'C' Display is 12/02/2019
04739 Very Dim
CR-PLP-2019- PY-1020D, Thermal Margin Monitor Channel 'D', Varies 12/03/2019
04747 more than the Other Channels
Miscellaneous System Health Engineered Safety Features Actuation System Q2 2019
Report
System Health Reactor System Protection Q2 2019
Report
Procedures EN-DC-205 Maintenance Rule Monitoring 7
EN-DC-206 Maintenance Rule (a)(1) Process 3
Work Orders WO 512169 P/S-0712, Replace AFAS (SCD) Power Supply 12/01/2018
WO 521490 AFAS Trip Alarm Due to P/S-0706 De-Energizing 03/25/2019
WO 521968 P/S-0704, Replace AFAS Power Supply 10/08/2019
WO 521972 P/S-0708, Replace AFAS Power Supply 06/11/2019
71111.13 Corrective Action CR-PLP-2019- NI 1/3A Wide Range Power Display was Found Reading 10/03/2019
Documents 03973 Approximately 10% Power
CR-PLP-2019- VC-10, Control Room HVAC Refrig Condensing Unit Trouble 11/02/2019
04406 Light on Panel C-11A
CR-PLP-2019- Received Alarm EK-0547, 125V DC Bus Ground 11/04/2019
04417 Unexpectedly
CR-PLP-2019- VC-10 (Control Room HVAC Refrigeration Condensing Unit) 11/04/2019
04420 Bearing was Damaged
CR-PLP-2019- VC-10 (Control Room H-VAC Compressor) Under Work 11/04/2019
04421 Order #533966 has Non-Conforming Parts
CR-PLP-2019- Main Exhaust Fan V6A Tripped on Overcurrent 11/04/2019
04430
Procedures EN-MA-157 Maintenance Configuration Control 10/02/2019
Inspection Type Designation Description or Title Revision or
Procedure Date
RI-99 Left Channel Nuclear Instrumentation Calibrations 10/22/2019
SOP-35 Neutron Monitoring System 17
Work Orders WO 531972 NI-1/3A Failed Low 10/1/2019
71111.15 Corrective Action CR-PLP-2019- NI-1/3A, Source & Wide Range Neutron Monitor Ch 1/3, 09/30/2019
Documents 03911 Appeared to Fail Low
CR-PLP-2019- NI-1/3A Wide Range Power Display was Found Reading 10/03/2019
03973 Approximately 10% Power
CR-PLP-2019- Carbon Steel Nuts had been Installed on the Stainless Steel 10/24/2019
275 Studs Between the Pump and the First Column
CR-PLP-2019- P-7A Service Water Pump Shim Packs are Loose on 12/09/2019
04832 Discharge Head to Floor Connection
Drawings E-61, Sheet 2A Schematic Diagram Source & Wide Range #1/3 Nuclear 6
Instrumentation
VEN-MI-RA, Neutron Flux Monitoring System Source & Wide Range 76
Sheet 857 Channels
Engineering EC 27090 Palisades EDG Turbo Support Cracking Report by MPR 0
Changes Associates
EC 37737 Approval of Spare Service Water Pump Bowl from Hydroaire 0
and Other Associated Components Not Previously Approved
by Other ECs
EC 84410 Operability Basis Input for Left Train Source/Wide Range 0
Nuclear Instrumentation, NI-1/3A
EC 84509 Operability Basis Input for EDG 1-1 (Emergency Diesel 0
Generator) Turbo Mount Cracks
EC 84714 Acceptability for Carbon Steel Nuts between P-7A Pump and 0
the First Column
Work Orders WO 506696 P-7A; Replace/Rebuild 10/23/2019
WO 52874649-1 K-6A Turbocharger Support Inspection 10/09/2019
71111.18 Calculations A13499-C-001 Evaluation of Service Water Pumps P-7A, 7B & 7C to 1
determine Feasibility of Removing the Lateral Bracket
Support at Elevation 583'
Corrective Action CR-PLP-2019- During performance of QO-14A Inservice Test PRocedure- 10/25/2019
Documents 04287 Service Water Pumps (WO-520027), Motor Outboard
Inspection Type Designation Description or Title Revision or
Procedure Date
Bearing vibration M1Z was measured in the "Alert Range"
CR-PLP-2019- P-7A, Service Water Pump Outboard Motor Radial M1Z was 11/26/2018
04705 recorded in "Alert Range" during QO-14A
Engineering EC 83228 Optional Removal of SW Pump Restraints Below 0
Changes Floor/Above Water
71111.19 Corrective Action CR-PLP-2019- Adjust A10-R30 in NI-1/3A to Adjust for Present Reactor 10/04/2019
Documents 03990 Power
Procedures QO-14 Inservice Test Procedure - Service Water Pumps 43
QO-19 Inservice Test Procedure - HPSI Pumps and ESS Check 43
Valve Operability Test
Work Orders WO 506696 P-7A; Replace/Rebuild 10/23/2019
WO 520027 QO-14A - P-7A, IST Service Water Pump 10/25/2019
WO 52819026 EEQ - EMA-1113 HPSI Pump P-66B Motor 10/16/2019
WO 52889284 QO-19B - High Pressure Safety Injection Pump & ESS 10/16/2019
Check Valve Operation
WO 531972-05 NI-1/3 Failed Low - Replace Drawer, (RTS) 10/14/2019
71111.22 Corrective Action CR-PLP-2019- Overvoltage Protection for P/S 0737A Work Instructions are 10/30/2019
Documents 04359 not Adequate for the Task
CR-PLP-2019- The PMID has not been Updated to Credit the Installation of 10/30/2019
04367 a New Calibrated Gauge as Due 1/22/2020
CR-PLP-2019- Temporary Installed Gauges Interfered with the Operation of 11/04/2019
04428 DPI-0319B Bypass Valve (IB) Which Caused Delays During
the Test to Adjust the Installed Gauges
Drawings M-204 Piping & Instrument Diagram Safety Injection Containment 41
Spray
VEN-M-107, SIRW Tank to Charging Pumps, Stress Isometric 03323 5
Sheet 4
VEN-M107, Stress Isometric Safety Injection, Containment Spray & 10
Sheet 2278 Shutdown Cooling System
Operability QO-21 Inservice Test Procedure - Auxiliary Feedwater Pumps 52
Evaluations
Procedures CEP-NDE-0902 VT-2 Examination Checklist for SIRW Tank 11/20/2019
QO-16 Inservice Test Procedure - Containment Spray Pumps 11/04/2019
QO-21 Inservice Test Procedure - Auxiliary Feedwater Pumps 52
Inspection Type Designation Description or Title Revision or
Procedure Date
RT-71M Class 2 System Inservice Test for Safety Injection and 11/20/2019
Refueling Water Tank
SOP-12 System Operating Procedure: Feedwater System 10/2/2019
SOP-4 Containment Spray System 27
Work Orders WO 52895070 QO-16B-P-54B, I&C Install Test Gauges 11/04/2019
71114.04 Miscellaneous 10 CFR50.54(Q) Training Documentation Record - 03/15/2018
McKinney
CFR50.54(Q) Training Documentation Record - Howard 11/15/2017
CFR50.54(Q) Training Documentation - Exemption 02/24/2012
Approval Form - D. Malone
CFR 50.54(Q)(3) Screening - Site Emergency Plan 09/18/18
Revision 31
CFR 50.54(Q)(3) Evaluation - Site Emergency Plan 09/18/18
Revision 31
SEP Site Emergency Plan 30
Procedures EN-EP-305 Emergency Planning 10CFR50.54(q) Review Program 6
SEP Site Emergency Plan 31
71124.01 Corrective Action CR-PLP-2018- Gate to T-69 Found Open 0/8/22/20018
Documents 03839
CR-PLP-2019- Increased Dose Rates in Primary System Drain Tank Room 11/09/2019
04491
Procedures EN-RP-106 Radiological Survey Documentation 7
EN-RP-121 Radioactive Material Control 16
EN-RP-131 Air Sampling 17
EN-RP-143 Source Control 14
Radiation PLP-1910-00005 590 Primary System Drain Tank Room 10/01/2019
Surveys PLP-1910-00074 649 Spent Fuel Pool Area 10/09/2019
PLP-1910-00100 649 Spent Fuel Pool Area 10/12/2019
PLP-1910-00104 East Engineered Safeguards 10/13/2019
PLP-1910-00216 East Engineered Safeguards 10/30/2019
PLP-2011-00028 590 Primary System Drain Tank Room 11/09/2019
PLP-2011-00033 590 Primary System Drain Tank Room 11/11/2019
PLP-2011-00034 590 Primary System Drain Tank Room 11/11/2019
Inspection Type Designation Description or Title Revision or
Procedure Date
Radiation Work 20190107 Decontamination and Housekeeping Activities in Locked 01
Permits (RWPs) High Radiation/High Radiation Areas/High Contamination
Areas
20190209 Activities Requiring Access to LHRAs 00
20190240 Dry Fuel Storage Campaign - Loading (MPC-37-05) (MPC- 02
37-06) (MPC-37-07) and Prep/Demob Activities
Self-Assessments LO-PLPLO-2019- 2019 Radiological Hazard Assessment and Exposure 09/18/2019
00011 Controls Self-Assessment
Work Orders 52738305 01 Perform Annual Rad Source Inventory 02/08/2018
2802850 01 Perform Annual Rad Source Inventory 02/14/2019
2823888 01 Offline Motor Electrical Testing 09/16/2019
71124.02 ALARA Plans ALARA Plan for RWP 2018-0444 10/17/2018
ALARA Plan for RWP 2018-0454 10/16/2018
ALARA Plan for RWP 2018-0450 11/20/2018
ALARA Plan for RWP 2018-0450 11/23/2018
ALARA Plan for RWP 2018-0434 10/16/2018
Miscellaneous Post Job ALARA Review for RWP 2018-0434 03/08/2019
40% Job In Progress Review for RWP 2018-0454 11/06/2018
Post Job ALARA Review for RWP 2018-0454 02/06/2019
80% Job In Progress Review for RWP 2018-0444 12/18/2018
40% Job In Progress Review for RWP 2018-0444 11/06/2018
Post Job ALARA Review for RWP 2018-0444 02/07/2019
Post Job ALARA Review for RWP 2018-0450 02/28/2019
40% Job In Progress Review for RWP 2018-0450 12/01/2018
80% Job In Progress Review for RWP 2018-0450 12/13/2018
40% Job In Progress Review for RWP 2018-0434 12/18/2018
80% Job In Progress Review for RWP 2018-0434 12/19/2018
Procedures EN-RP-105 Radiological Work Permits 18
Radiation Work 2018-0434 Refuel Project: Reassembly of the Reactor Head and 00
Permits (RWPs) Associated Work Activities
2018-0444 Reactor Head Inspection: Removal/Installation of Control 00
Rod Drive Seal Housing Packages and Removal/Installation
of Control Rod Drive Mechanism Drive Motors.
Inspection Type Designation Description or Title Revision or
Procedure Date
2018-0450 1R26 Emergent Reactor Head Nozzle Repair and Support 06
Activities
2018-0454 Steam Generator Primary Side Activities 00
71124.05 Work Orders 52770033 RI-86G-2 High Range Containment Monitor Calibration 01/17/2019
2777256 RI-86G-1 - High Range Containment Monitor Calibration - 11/04/2018
Source Test
71124.08 Corrective Action CR-PLP-2018- Radiation Monitor is East Rad Waste Removed from Service 01/18/2018
Documents 00297 Due to Spurious Auto-Dialer Alarms in the Control Room
CR-PLP-2018- Troubleshoot and Repair Nuisance Auto-Dialer Alarms at 03/15/2018
215 East Rad Waste
CR-PLP-2018- Auto-Dialer Alarm Function Found Unplugged from 10/17/2018
04820 Radiation Monitor in East Radwaste Building
CR-PLP-2019- Prioritize Repair of the Auto-Dial Control Room Alarm 01/24/2019
247 Function for the East Rad Waste Radiation Monitor
Miscellaneous Memo To From Palisades Plant - Shippers Qualifications 2018 REvision 05/30/2018
JLSmith
Procedures DM-OP-046- Operation of the Energy Solutions ALPS System at 11
161046 Palisades Nuclear Power Station
EN-RW-102 Radioactive Waste Shipping 17
EN-RW-104 Scaling Facators 13
EN-RW-106 Integrated Transportation Security Plan 6
Self-Assessments LO-PLPLO-2019- Pre-NRC Inspection Radioactive Solid Waste Processing 07/10/2019
00010 and Radioactive Material Handling, Storage and
Transportation Self-Assessment
Shipping Records 2017-RW-017 8-120-B Metal Cask with Poly HIC Liner Containing T-100 10/30/2017
Resins
2018-RW-004 3-60B-1 Metal Cask with 3-60 Steel Liner containing 03/06/2019
Irradiated Hardware
2018-RW-007 14-170-32 Metal Cask containing High Rad Metal Waste in 09/13/2018
Liner
2018-RW-011 (2) 20' Sea Lands containing Dry Active Waste & Metal 11/07/2018
Waste for Processing
Work Orders 00486643 East Radwaste Auto-Dialer Bringing in Nuisance Alarms 10/17/2017
71151 Corrective Action CR-PLP-2019- Diesel Generator 1-1 Service Water Flow was Reading 10/07/2019
Inspection Type Designation Description or Title Revision or
Procedure Date
Documents 04023 Elevated at 710 gpm
Miscellaneous MSPI Derivation MSPI Derivation Documents for October 1, 2018 through 10/01/2018 -
Documents September 30, 2019 09/30/2019
71152 Corrective Action CR-PLP-2019- Operating Crew Missed the Window to Block MSIV Closure 07/28/2019
Documents 02920
CR-PLP-2019- Three-Year Trend of Power Supply Failures 08/15/2019
229
CR-PLP-2019- Unplanned Transfer of Water to SIRWT 09/04/2019
03474
CR-PLP-2019- Emergency Diesel Generator 1-1 Test, TI-1481, K-6A Jacket 10/07/2019
04024 Water Temperature Indicator was Reading 140 Degrees
Fahrenheit
CR-PLP-2019- CRDM Cooling Fan Tripped 10/25/2019
292
CR-PLP-2019- Aggregate Performance Issue (AP) Associated with Rework 11/18/2019
04583 Performance Rated
CR-PLP-2019- Large Amounts of Boric Acid under P-54C, Containment 11/23/2019
04674 Spray Pump
CR-PLP-2019- CRDM Cooling Fan V-49A Failure 12/07/2019
04824
CR-PLP-2019- Create a Contigency Work Order with Four Tasks to Replace 12/17/2019
04935 any Thermo Margin Monitor CRT Display Screens
CR-PLP-2019- NIOS Identified: Problem Identified During Review of 12/19/2019
05001 CR-PLP-2019-03474
Miscellaneous APRM Report Palisades Performance Improvement 08/2019
Procedures Admin 4.02 Control of Equipment 82
EN-HU-102 Human Performance Traps and Tools 16
GOP-9 Mode 3 > 525F to Mode 4 or Mode 5 37
SOP-27 Fuel Pool System 72
71153 Miscellaneous 05000255 Indications Identified in Reactor Pressure Vessel Head 01
Nozzle Penetrations
25