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
January 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:
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
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 Palisades Nuclear Plant,
Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations 71153 Closed
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 Sample)
- (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) (3 Samples)
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 Sample)
- (1) The inspectors evaluated fire brigade performance during a drill on November 8, 2019
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (3 Samples)
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.) (1 Sample)
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) (1 Sample)
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 Sample)
- (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 Sample)
- (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) (2 Samples)
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) (3 Samples)
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) (4 Samples)
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) (1 Sample)
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) (4 Samples)
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 Sample)
- (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) (1 Sample)
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)===
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) (1 Sample)
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) (1 Sample)
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 Sample)
- (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
Procedure
Type
Designation
Description or Title
Revision or
Date
60855.1
ALARA Plans
Radiological Work Permits
Corrective Action
Documents
Review of Selected Corrective Action Reports Since
January 2017
CR-PLP-2016-
05475
HI-STORM FW Combustible Controls
11/16/2016
Engineering
Changes
Perform Modification to Change the East Trolley Limit Switch
on L-3 per CR 2016-4562
Miscellaneous
Certificate of Compliance No. 1032, Amendment No. 1
Final Safety Analysis Report on the HI-STORM FW MPC
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
HI-TRAC Lift Bracket Bolt Inspection per HSP-366
10/02/2019
Certificates of Conformance for Purchase Order 107236
08/12/2015
DOC-103-007R2
Leased HI-TRAC VW for Use at Palisades (Entergy)
Documentation Package
09/26/2019
DOC-104-107-
016R1
Leased MPC-37 Lift Bracket for HI-STORM FW
Documentation Package
06/25/2019
DOC-104-209-
018R1
Leased MPC-37 Lift Cleat Documentation Package
06/25/2019
DOC-104-702-
23R1
Leased HI-TRAC VW Lift Yoke to Palisades Documentation
Package
06/25/2019
DOC-104-731-
019R1
Leased MPC Lid Lift Adapter and MPC Lid Lift Rigging
Documentation Package
06/25/2019
DOC-2251-
004R1
Lower Fuel Shims for Palisades Nuclear Plant
Documentation Package
08/09/2019
DTF-3005-015B
Palisades Training Records
09/24/2019
MPC Loading Plan for MPC 123, 124 and 125
Revision 4
PROC No.
FSHO-17A
MPC-37 Fuel Verification
10/01/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Report No. PLP
21032
Palisades 10 CFR 72.212 Evaluation Report
09/09/2019
NDE Reports
Report No.
915741-123-01
Report of Visual Non-Destructive Examination
10/04/2010
Annual Crane Liquid Penetrant Examination
08/08/2019
Procedures
AT-36
ISFSI Pad Monitoring Program
AT-9
Examination of Ventilated Concrete Cask Assembly Exterior
GQP - 9.2
High Temperature Liquid Penetrant Examination and
Acceptance Standards for Welds, Base Materials and
Cladding (50° - 350°F)
GQP - 9.6
Visual Examination of Welds
Procedure No.
FHS-M-41B
HI-STORM FW Dry Fuel Loading Operations - MPC Loading
Procedure No.
FHS-M-41C
HI-STORM FW Dry Fuel Loading Operations - MPC Sealing
and Drying
Procedure No.
FHS-M041D
HI-STORM FW Dry Fuel Loading Operations - MPC Transfer
to HI-STORM
Radiation
Surveys
Periodic Radiological Surveys Performed Since
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
Completion
Limits on Crane are Not Working Properly - Investigate
07/25/2019
AT-9 Dry Fuel Storage Cask Exterior Inspection
06/04/2019
AT-36 ISFSI Pad Monitoring Program
07/25/2019
Corrective Action
Documents
Resulting from
Inspection
CR-PLP-2019-
04653
NRC Identified Gaps in Insulation
11/21/2019
CR-PLP-2019-
04723
NRC Resident Identified a Cable/Extension Cord Hanging
Over the Edge of the Roof on the North Side of the Turbine
Building
11/27/2019
CR-PLP-2019-
04807
Unsecure Items Identified by the NRC
2/06/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
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
Procedures
Acts of Nature
Diesel Fuel Oil Program
EN-FAP-EP-010
7.14, Severe Weather Missile Hazard Reduction
Guidance
SOP-15
Service Water System
SOP-23
Plant Heating System
Work Orders
Perform Cold Weather Checksheets
10/23/2019
71111.04Q Corrective Action
Documents
CR-PLP-2019-
01047
A Small Puddle of Fuel Oil was Noticed on the Floor Below
MV-FO705, P-18A/B Discharge to FO Day Tank T-40
03/13/2019
CR-PLP-2019-
2813
HP Air Compressor in West Safeguards was Found to Have
a Minor Leak
07/19/2019
CR-PLP-2019-
04084
MV-CC942, Component Cooling Water (CCW) P-52B
Discharge, has Evidence of Past Leakage on the East Side
of the Upper Flange
10/10/2019
CR-PLP-2019-
04344
Observed Roof Leak of ~60-80 Drops per Minute on West
Side of 625' Elevation of Turbine Deck
10/30/2019
CR-PLP-2019-
04369
CK-FW743, Auxiliary Feedwater Pump P-8B has a Body to
Bonnet Leak of 5 Drops per Minute
10/31/2019
Corrective Action
Documents
Resulting from
Inspection
CR-PLP-2019-
04101
NRC Identified a Large Amount of Carbon Build Up on the
Southwest Portion of the Turbocharger
10/11/2019
Drawings
M-214, Sheet 1
Piping & Instrument Diagram, Lube Oil, Fuel Oil, & Diesel
Generator Systems
Miscellaneous
DBD-1.03
Design Basis Document for Auxiliary Feedwater System
Procedures
SOP-12,
14
Auxiliary Feedwater System Checklist
SOP-22
Procedures
PLDRL-FBT-FIREDRILL (19-018)
11/08/2019
Fire Drill Report
11/15/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.05Q Fire Plans
Pre Fire Plan
Area 10
East Engineered Safeguards Room/ Elevation 570'
Pre Fire Plan
Area 23
Turbine Building - South / Elevation 590'
Pre Fire Plan
Area 9
Screen House / Intake Structure / Elevation 590'
Procedures
Control of Combustibles
Calculations
EA-C-PAL-95-
26-01
Internal Flooding Evaluation for Plant Areas Outside
Contaiment
3a
Corrective Action
Documents
CR-PLP-2019-
04899
PMID 50083994-02 May Not be Effective
2/13/2019
CR-PLP-2019-
04945
Two of Three Drains in Cable Spreading are Plugged
2/17/2019
Corrective Action
Documents
CR-PLP-2019-
01138
Eddy Current Testing of the E-31B "EDG 1-2 Lube Oil
Cooler"
03/19/2019
Procedures
EPS-M-14A
Diesel Generator Every Cycle Maintenance
03/18/2019
SEP-HX-PLP-001 Supplemental HX Visual Inspection Checklist - Jacket Water
Cooler
03/18/2019
Work Orders
2771367-01
K-6B 1-2 D/G 24 Month PM
03/18/2019
Miscellaneous
Palisades Annual Licensed Operator Requalification
Summary Results for 2019
3/29/2019
71111.11Q Corrective Action
Documents
CR-PLP-2019-
224
The CRT Screen for PY-0102A 'A' Channel Thermal Margin
Monitor is Growing Dim
10/21/2019
CR-PLP-2019-
04476
During Training, Instructor Identified that the InForm
Program was Configured to the "Palisades" Jurisdiction
11/07/2019
Corrective Action
Documents
CR-PLP-2018-
05433
EC-187D, AFAS Sensor Channel Cabinet, has No 12 Volt
DC Power
11/02/2018
CR-PLP-2019-
213
Received EK-0137, Auxilary Feedwater AFAS-FOGG
Subsystem Trip
03/23/2019
CR-PLP-2019-
222
P/S-0712 from CR-PLP-2018-05433 was Not Sent to the
Vendor for Failure Analysis
03/25/2019
CR-PLP-2019-
03549
Maintenance Rule (a)(1) Action Plan, Thermal Margin
Monitor (TMM) Displays
2/04/2019
CR-PLP-2019-
PY-0102C: Thermal Margin Monitor Channel 'C' Display has
09/14/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
03687
Dimmed in is now Unreadable
CR-PLP-2019-
04016
Two Maintenance Rule Repeat Functional Failures
Associated with the Thermal Margin Monitors (TMM)
10/07/2019
CR-PLP-2019-
04540
Documented Failures of TMM Circuit Cards
11/14/2019
CR-PLP-2019-
04603
NI-07 Power Range Instrumentation
11/19/2019
CR-PLP-2019-
04739
PY-0102C: Thermal Margin Monitor Channel 'C' Display is
Very Dim
2/02/2019
CR-PLP-2019-
04747
PY-1020D, Thermal Margin Monitor Channel 'D', Varies
more than the Other Channels
2/03/2019
Miscellaneous
System Health
Report
Engineered Safety Features Actuation System
Q2 2019
System Health
Report
Reactor System Protection
Q2 2019
Procedures
Maintenance Rule Monitoring
Maintenance Rule (a)(1) Process
Work Orders
P/S-0712, Replace AFAS (SCD) Power Supply
2/01/2018
AFAS Trip Alarm Due to P/S-0706 De-Energizing
03/25/2019
P/S-0704, Replace AFAS Power Supply
10/08/2019
P/S-0708, Replace AFAS Power Supply
06/11/2019
Corrective Action
Documents
CR-PLP-2019-
03973
NI 1/3A Wide Range Power Display was Found Reading
Approximately 10% Power
10/03/2019
CR-PLP-2019-
04406
VC-10, Control Room HVAC Refrig Condensing Unit Trouble
Light on Panel C-11A
11/02/2019
CR-PLP-2019-
04417
Received Alarm EK-0547, 125V DC Bus Ground
Unexpectedly
11/04/2019
CR-PLP-2019-
04420
VC-10 (Control Room HVAC Refrigeration Condensing Unit)
Bearing was Damaged
11/04/2019
CR-PLP-2019-
04421
VC-10 (Control Room H-VAC Compressor) Under Work Order #533966 has Non-Conforming Parts
11/04/2019
CR-PLP-2019-
04430
Main Exhaust Fan V6A Tripped on Overcurrent
11/04/2019
Procedures
Maintenance Configuration Control
10/02/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
RI-99
Left Channel Nuclear Instrumentation Calibrations
10/22/2019
SOP-35
Neutron Monitoring System
Work Orders
NI-1/3A Failed Low
10/1/2019
Corrective Action
Documents
CR-PLP-2019-
03911
NI-1/3A, Source & Wide Range Neutron Monitor Ch 1/3,
Appeared to Fail Low
09/30/2019
CR-PLP-2019-
03973
NI-1/3A Wide Range Power Display was Found Reading
Approximately 10% Power
10/03/2019
CR-PLP-2019-
275
Carbon Steel Nuts had been Installed on the Stainless Steel
Studs Between the Pump and the First Column
10/24/2019
CR-PLP-2019-
04832
P-7A Service Water Pump Shim Packs are Loose on
Discharge Head to Floor Connection
2/09/2019
Drawings
E-61, Sheet 2A
Schematic Diagram Source & Wide Range #1/3 Nuclear
Instrumentation
VEN-MI-RA,
Sheet 857
Neutron Flux Monitoring System Source & Wide Range
Channels
Engineering
Changes
Palisades EDG Turbo Support Cracking Report by MPR
Associates
Approval of Spare Service Water Pump Bowl from Hydroaire
and Other Associated Components Not Previously Approved
by Other ECs
Operability Basis Input for Left Train Source/Wide Range
Nuclear Instrumentation, NI-1/3A
Operability Basis Input for EDG 1-1 (Emergency Diesel
Generator) Turbo Mount Cracks
Acceptability for Carbon Steel Nuts between P-7A Pump and
the First Column
Loose Shim on P-7A
Work Orders
P-7A; Replace/Rebuild
10/23/2019
WO 52874649-1
K-6A Turbocharger Support Inspection
10/09/2019
Calculations
A13499-C-001
Evaluation of Service Water Pumps P-7A, 7B & 7C to
determine Feasibility of Removing the Lateral Bracket
Support at Elevation 583'
Corrective Action
Documents
CR-PLP-2019-
287
During performance of QO-14A Inservice Test PRocedure-
Service Water Pumps (WO-520027), Motor Outboard
10/25/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Bearing vibration M1Z was measured in the "Alert Range"
CR-PLP-2019-
04705
P-7A, Service Water Pump Outboard Motor Radial M1Z was
recorded in "Alert Range" during QO-14A
11/26/2018
Engineering
Changes
Optional Removal of SW Pump Restraints Below
Floor/Above Water
Corrective Action
Documents
CR-PLP-2019-
03990
Adjust A10-R30 in NI-1/3A to Adjust for Present Reactor
Power
10/04/2019
Procedures
QO-14
Inservice Test Procedure - Service Water Pumps
QO-19
Inservice Test Procedure - HPSI Pumps and ESS Check
Valve Operability Test
Work Orders
P-7A; Replace/Rebuild
10/23/2019
QO-14A - P-7A, IST Service Water Pump
10/25/2019
EEQ - EMA-1113 HPSI Pump P-66B Motor
10/16/2019
QO-19B - High Pressure Safety Injection Pump & ESS
Check Valve Operation
10/16/2019
NI-1/3 Failed Low - Replace Drawer, (RTS)
10/14/2019
Corrective Action
Documents
CR-PLP-2019-
04359
Overvoltage Protection for P/S 0737A Work Instructions are
not Adequate for the Task
10/30/2019
CR-PLP-2019-
04367
The PMID has not been Updated to Credit the Installation of
a New Calibrated Gauge as Due 1/22/2020
10/30/2019
CR-PLP-2019-
04428
Temporary Installed Gauges Interfered with the Operation of
DPI-0319B Bypass Valve (IB) Which Caused Delays During
the Test to Adjust the Installed Gauges
11/04/2019
Drawings
M-204
Piping & Instrument Diagram Safety Injection Containment
Spray
VEN-M-107,
Sheet 4
SIRW Tank to Charging Pumps, Stress Isometric 03323
VEN-M107,
Sheet 2278
Stress Isometric Safety Injection, Containment Spray &
Shutdown Cooling System
Operability
Evaluations
QO-21
Inservice Test Procedure - Auxiliary Feedwater Pumps
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
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Class 2 System Inservice Test for Safety Injection and
Refueling Water Tank
11/20/2019
SOP-12
System Operating Procedure: Feedwater System
10/2/2019
SOP-4
Containment Spray System
Work Orders
QO-16B-P-54B, I&C Install Test Gauges
11/04/2019
Miscellaneous
CFR50.54(Q) Training Documentation Record -
McKinney
03/15/2018
CFR50.54(Q) Training Documentation Record - Howard
11/15/2017
CFR50.54(Q) Training Documentation - Exemption
Approval Form - D. Malone
2/24/2012
CFR 50.54(Q)(3) Screening - Site Emergency Plan
Revision 31
09/18/18
CFR 50.54(Q)(3) Evaluation - Site Emergency Plan
Revision 31
09/18/18
Site Emergency Plan
Procedures
Emergency Planning 10CFR50.54(q) Review Program
Site Emergency Plan
Corrective Action
Documents
CR-PLP-2018-
03839
Gate to T-69 Found Open
0/8/22/20018
CR-PLP-2019-
04491
Increased Dose Rates in Primary System Drain Tank Room
11/09/2019
Procedures
Radiological Survey Documentation
Radioactive Material Control
Air Sampling
Source Control
Radiation
Surveys
590 Primary System Drain Tank Room
10/01/2019
649 Spent Fuel Pool Area
10/09/2019
649 Spent Fuel Pool Area
10/12/2019
East Engineered Safeguards
10/13/2019
East Engineered Safeguards
10/30/2019
590 Primary System Drain Tank Room
11/09/2019
590 Primary System Drain Tank Room
11/11/2019
590 Primary System Drain Tank Room
11/11/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Radiation Work
Permits (RWPs)
20190107
Decontamination and Housekeeping Activities in Locked
High Radiation/High Radiation Areas/High Contamination
Areas
20190209
Activities Requiring Access to LHRAs
20190240
Dry Fuel Storage Campaign - Loading (MPC-37-05) (MPC-
37-06) (MPC-37-07) and Prep/Demob Activities
Self-Assessments LO-PLPLO-2019-
00011
2019 Radiological Hazard Assessment and Exposure
Controls Self-Assessment
09/18/2019
Work Orders
2738305 01
Perform Annual Rad Source Inventory
2/08/2018
2802850 01
Perform Annual Rad Source Inventory
2/14/2019
2823888 01
Offline Motor Electrical Testing
09/16/2019
ALARA Plans
10/17/2018
10/16/2018
11/20/2018
11/23/2018
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
2/06/2019
80% Job In Progress Review for RWP 2018-0444
2/18/2018
40% Job In Progress Review for RWP 2018-0444
11/06/2018
Post Job ALARA Review for RWP 2018-0444
2/07/2019
Post Job ALARA Review for RWP 2018-0450
2/28/2019
40% Job In Progress Review for RWP 2018-0450
2/01/2018
80% Job In Progress Review for RWP 2018-0450
2/13/2018
40% Job In Progress Review for RWP 2018-0434
2/18/2018
80% Job In Progress Review for RWP 2018-0434
2/19/2018
Procedures
Radiological Work Permits
Radiation Work
Permits (RWPs)
2018-0434
Refuel Project: Reassembly of the Reactor Head and
Associated Work Activities
2018-0444
Reactor Head Inspection: Removal/Installation of Control
Rod Drive Seal Housing Packages and Removal/Installation
of Control Rod Drive Mechanism Drive Motors.
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2018-0450
1R26 Emergent Reactor Head Nozzle Repair and Support
Activities
2018-0454
Steam Generator Primary Side Activities
Work Orders
2770033
RI-86G-2 High Range Containment Monitor Calibration
01/17/2019
2777256
RI-86G-1 - High Range Containment Monitor Calibration -
Source Test
11/04/2018
Corrective Action
Documents
CR-PLP-2018-
297
Radiation Monitor is East Rad Waste Removed from Service
Due to Spurious Auto-Dialer Alarms in the Control Room
01/18/2018
CR-PLP-2018-
215
Troubleshoot and Repair Nuisance Auto-Dialer Alarms at
East Rad Waste
03/15/2018
CR-PLP-2018-
04820
Auto-Dialer Alarm Function Found Unplugged from
Radiation Monitor in East Radwaste Building
10/17/2018
CR-PLP-2019-
247
Prioritize Repair of the Auto-Dial Control Room Alarm
Function for the East Rad Waste Radiation Monitor
01/24/2019
Miscellaneous
Memo To From
JLSmith
Palisades Plant - Shippers Qualifications 2018 REvision
05/30/2018
Procedures
DM-OP-046-
161046
Operation of the Energy Solutions ALPS System at
Palisades Nuclear Power Station
Radioactive Waste Shipping
Scaling Facators
Integrated Transportation Security Plan
Self-Assessments LO-PLPLO-2019-
00010
Pre-NRC Inspection Radioactive Solid Waste Processing
and Radioactive Material Handling, Storage and
Transportation Self-Assessment
07/10/2019
Shipping Records 2017-RW-017
8-120-B Metal Cask with Poly HIC Liner Containing T-100
Resins
10/30/2017
2018-RW-004
3-60B-1 Metal Cask with 3-60 Steel Liner containing
Irradiated Hardware
03/06/2019
2018-RW-007
14-170-32 Metal Cask containing High Rad Metal Waste in
Liner
09/13/2018
2018-RW-011
(2) 20' Sea Lands containing Dry Active Waste & Metal
Waste for Processing
11/07/2018
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
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
04023
Elevated at 710 gpm
Miscellaneous
MSPI Derivation
Documents
MSPI Derivation Documents for October 1, 2018 through
September 30, 2019
10/01/2018 -
09/30/2019
Corrective Action
Documents
CR-PLP-2019-
2920
Operating Crew Missed the Window to Block MSIV Closure
07/28/2019
CR-PLP-2019-
229
Three-Year Trend of Power Supply Failures
08/15/2019
CR-PLP-2019-
03474
Unplanned Transfer of Water to SIRWT
09/04/2019
CR-PLP-2019-
04024
Emergency Diesel Generator 1-1 Test, TI-1481, K-6A Jacket
Water Temperature Indicator was Reading 140 Degrees
Fahrenheit
10/07/2019
CR-PLP-2019-
292
CRDM Cooling Fan Tripped
10/25/2019
CR-PLP-2019-
04583
Aggregate Performance Issue (AP) Associated with Rework
Performance Rated
11/18/2019
CR-PLP-2019-
04674
Large Amounts of Boric Acid under P-54C, Containment
Spray Pump
11/23/2019
CR-PLP-2019-
04824
CRDM Cooling Fan V-49A Failure
2/07/2019
CR-PLP-2019-
04935
Create a Contigency Work Order with Four Tasks to Replace
any Thermo Margin Monitor CRT Display Screens
2/17/2019
CR-PLP-2019-
05001
NIOS Identified: Problem Identified During Review of
2/19/2019
Miscellaneous
APRM Report
Palisades Performance Improvement
08/2019
Procedures
Admin 4.02
Control of Equipment
Human Performance Traps and Tools
GOP-9
Mode 3 > 525F to Mode 4 or Mode 5
SOP-27
Fuel Pool System
Miscellaneous
05000255
Indications Identified in Reactor Pressure Vessel Head
Nozzle Penetrations
01