IR 05000255/2020002
| ML20224A204 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/11/2020 |
| From: | April Nguyen NRC/RGN-III |
| To: | Corbin D Entergy Nuclear Operations |
| References | |
| EA-17-115 IR 2020002 | |
| Download: ML20224A204 (19) | |
Text
August 11, 2020
SUBJECT:
PALISADES NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000255/2020002 AND EXERCISE OF ENFORCEMENT DISCRETION
Dear Mr. Corbin:
On June 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palisades Nuclear Plant. On July 23, 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/
April M. Nguyen, Acting Chief Branch 2 Division of Reactor Projects
Docket No. 05000255 License No. DPR-20
Enclosure:
As stated
Inspection Report
Docket Number:
05000255
License Number:
Report Number:
Enterprise Identifier: I-2020-002-0033
Licensee:
Entergy Nuclear Operations, Inc.
Facility:
Palisades Nuclear Plant
Location:
Covert, MI
Inspection Dates:
April 1, 2020 to June 30, 2020
Inspectors:
J. Benjamin, Senior Reactor Inspector
P. Laflamme, Senior Resident Inspector
J. Mancuso, Resident Inspector
V. Myers, Senior Health Physicist
C. St. Peters, Resident Inspector
Approved By:
April M. Nguyen, Acting 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 EDG EA-17-115 Enforcement Action EA-17-115: Enforcement Discretion for Tornado Missile Protection Non-Conforming Conditions 71111.15 Discussed
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 reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time the resident inspectors performed periodic site visits each week and during that time conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities, and completed on-site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on-site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated summer readiness of offsite and alternating current (AC) power systems on June 3, 2020
External Flooding Sample (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding on June 9, 2020
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Emergency diesel generator (EDG) 1-1 on April 23, 2020
- (2) Right train high pressure safety injection (HPSI) system on June 3, 2020
- (3) Left train low pressure safety injection (LPSI) system on June 15, 2020
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations while performing a complete walkdown of the right train auxiliary feedwater (AFW) system during the week of May 18, 2020
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Fire Area 24: AFW pump room, elevation 571' on April 10, 2020
- (2) Fire Areas 5 & 7: 1-1 diesel generator and fuel oil day tank rooms, elevation 590' on April 24, 2020
- (3) Fire Area 33: Technical Support Center, elevation 625' on May 7, 2020
- (4) Fire Area 1: Control Room, elevation 625' on June 29, 2020
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 PLSEG-LOR-20B-04 on June 19, 2020
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
- (1) Thermal margin monitoring system on April 20, 2020
- (2) Primary coolant system on May 29, 2020
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Risk management activities and emergent work for P1-A, main feedwater pump (MFP), recirculation valve steam leak on April 23, 2020
- (2) Emergent troubleshooting and work management activities associated with letdown system pressure control on April 29, 2020
- (3) Elevated risk for planned shutdown cooling system testing on June 10, 2020
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Review of identified tornado missile protection nonconformance during the week of April 6, 2020
- (2) Thermal margin monitor channel A operability evaluation on May 5, 2020
- (3) Quench tank pressure rise evaluation on June 25, 2020
- (4) Pressurizer heater breaker friction block evaluation on June 26, 2020
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) Temporary modification to CV-944A manual side packing on April 17, 2020
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:
- (1) Control Room ventilation system testing following planned maintenance activities on April 27, 2020
- (2) Letdown stop valve orifice testing following planned maintenance activities on May 7, 2020
- (3) CV-0711, P-1A MFP recirculation valve testing following body to bonnet steam leak repairs on May 14, 2020
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
(1)1-2 EDG monthly surveillance test on April 21, 2020
- (2) Reactor protection matrix logic quarterly surveillance test on June 3, 2020
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) QO-42, shutdown cooling valves test on June 10, 2020
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) FLEX Standby PM: P-1003, One Year Operational Test on April 14,
RADIATION SAFETY
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees use of respiratory protection devices
Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)
- (1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses
71124.04 - Occupational Dose Assessment
Source Term Characterization (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization
External Dosimetry (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated licensee performance as it pertains to external dosimetry that is used to assign occupational dose
Special Dosimetric Situations (IP Section 03.04) (2 Samples)
The inspectors evaluated the following special dosimetric situations:
- (1) Dose assessment for a declared pregnant worker in 2019
- (2) Effective dose equivalent assessment for individual performing reactor head work in
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 02.02)
=
- (1) Unit 1 (April 1, 2019-March 31, 2020)
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (1 Sample)
- (1) Unit 1 (April 1, 2019-March 31, 2020)
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends with a focus on human performance issues that might be indicative of a more significant safety issue during the period from January 1, 2020 to June 30, 2020
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) Letdown relief valve lift and subsequent isolation adverse condition analysis, as documented in CR-PLP-2020-00611, during the week of May 18, 2020
71153 - Follow-up of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) Licensee Event Reports 05000255/2017-001-00/01, "Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Conditions" retraction
This LER was submitted and subsequently retracted LERs 05000255/2017-001-00(01) by licensee correspondence titled "Cancellation of Licensee Event Reports 2017-001-00 and 2017-001-01, "Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design Conditions", dated March 31, 2020, ADAMS Accession No. ML20091J599. The inspectors reviewed the LER and completed an inspection sample listed under 71111.15, Operability Determination, of this report.
INSPECTION RESULTS
EDG (Discussed)
Enforcement Action EA-17-115: Enforcement Discretion for Tornado Missile Protection Non-Conforming Conditions EDG 71111.15
Description:
On June 10, 2015, the NRC issued Regulatory Issue Summary 2015-06, Tornado Missile Protection, focusing on the requirements regarding tornado-generated missile protection and required compliance with the facility-specific licensing basis. The Regulatory Issue Summary also provided examples of noncompliances that had been identified through different mechanisms and referenced Enforcement Guidance Memorandum (EGM) 15-002, which was also issued on June 10, 2015. Revision 1 of EGM 15-002 was issued on February 7, 2017. The EGM revision provided guidance to allow the NRC staff to exercise enforcement discretion when an operating power plant licensee did not comply with the current licensing basis for tornado-generated missile protection. Specifically, the discretion applied to structures, systems, and components (SSCs) declared inoperable resulting in TS Limiting Conditions for Operation (LCOs) that would require a reactor shutdown or mode change if the licensee could not meet the required actions within the TS completion time. The discretion allowed the licensee to re-establish operability through compensatory measures and established criteria for continued operation of the facility as longer-term corrective actions were implemented.
On March 29, 2017, the licensee initiated condition reports (CRs) CR-PLP-2017-01248, CR-PLP-2017-01249, CR-PLP-2017-01250, CR-PLP-2017-01251, CR-PLP-2017-01252, and CR-PLP-2017-01253, identifying multiple nonconforming conditions of their site-specific licensing basis. Specifically, the licensee identified multiple non-conforming conditions related to inadequate tornado-generated missile protection. The licensee declared multiple SSCs inoperable, promptly implemented interim compensatory measures, and subsequently exited the TS LCO action statements based upon NRC EGM 15-002 guidelines. The NRC documented additional information in Integrated Inspection Report 05000255/2018001.
On January 20, 2020, the licensee completed a tornado missile nonconformance review to document the licensing basis for Palisades tornado missile protection features, specifically regarding the non-conforming issues identified as a result of NRC Regulatory Issue Summary 2015-06. The licensees review concluded that the previously identified non-conforming issues were, in fact, conforming to the current licensing basis. As such, the licensee concluded that corrective actions were not required to restore compliance.
The inspectors reviewed the licensees nonconformance review documented in Engineering Change (EC) 85113, condition reports initiated by the licensee, historic NRC correspondence, aspects of the original conditional operating license and final operating license, the original FSAR, the UFSAR, related safety evaluation report correspondence, the incorporation of the Systematic Evaluation Program into the current licensing basis and other documents provided in the documents reviewed section of this report. Consistent with the licensees review documented in EC 85113, the inspectors did not identify any non-conforming conditions, findings or violations. As a result, no corrective actions are required and EA-17-115 is considered closed.
Observation: Semi-Annual Trend Review 71152 The inspectors review was focused on human performance issues, 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 January 2020 through June 2020, although some examples expanded beyond those dates when warranted by the scope of the trend.
The inspectors reviewed condition reports, trend reports, and human performance evaluations to address performance oversight at the site. During the inspection period, the NRC inspectors noted a few challenges where low-level human performance errors occurred in multiple departments, including Operations, Maintenance, Security, and Training.
Examples included the operation of a breaker failure relay during maintenance activities which resulted in an unexpected trip of the switchyard 345 kV rear bus, not all required sections of Simulator Exercise Guide (SEG) being covered during the Licensed Operator initial simulator training, a level-3 tagging error, a missed window to block MSIV closure, and an unplanned water transfer to SIRWT. Although the above examples did not challenge safety function or equipment reliability, these issues illustrated a decline in the use of human performance tools, which could potentially impact nuclear safety.
The licensee appropriately entered these issues into the CAP and completed timely evaluations addressing each challenge listed above. Corrective actions included training, site-wide communications reinforcing standards and expectations, and a re-emphasis on the following human performance tools: pre-job briefs; procedure use and adherence; and verification and validation activities. The inspectors determined that the corrective actions taken to date appeared to be effective at addressing the identified gaps and plan to continue to evaluate these actions during routine observations and inspections.
Observation: Letdown Relief Valve Lift Adverse Condition Analysis Review 71152 The inspectors reviewed the events, circumstances, and causal evaluation associated with the letdown relief valve, RV-2006, lift that occurred on February 25, and again on March 4, 2020. Their efforts included assessing the licensee's Failure Mode Analysis (FMA),troubleshooting, trending, and aggregate review activities. Additionally, the inspectors reviewed primary coolant system leakage trends, equipment condition assessments for the letdown system, monthly containment tour results, and quench tank level monitoring. The inspectors also interviewed operators, maintenance workers, and engineering personnel to complete their assessment efforts. In their review, the inspectors noted that the direct cause of relief valve lift was attributed to a localized pressure transient in the letdown system resulting from the intermediate letdown pressure controller timing sensitivity coupled with gas void collapse at the relief valve seat. For corrective actions, the licensee replaced RV-2006 and re-tuned the intermediate letdown pressure controller, which resulted in stabilizing system pressure. Therefore, since the licensee sufficiently determined the direct cause of relief valve lift and successfully completed corrective actions, the inspectors concluded the licensee actions taken were timely and effective commensurate with safety significance.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 23, 2020, the inspectors presented the integrated inspection results to Mr. D. Corbin, Site Vice President, and other members of the licensee staff.
- On May 13, 2020, the inspectors presented the radiation protection inspection results to Mr. D. Corbin, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-PLP-2020-
01398
Boot Seals on South Wall (Containment) of Room 121 A
(Dog House)
05/01/2020
CR-PLP-2020-
01864
Lake Michigan Level has Potentially Exceeded the Design
Basis Elevation of 583.2 ft MSL
06/10/2020
Engineering
Changes
Revise Flooding Analysis to Reflect Changes in Plant
Configuration
Revision 0
Miscellaneous
Engineering
Information
Record 51-
26987-000
Palisades Nuclear Plant Flooding Hazard Re-Evaluation
Report
05/09/2015
Required - Response 2 for Near-Term Task Force
Recommendation 2.1: Flooding - Hazard Re-Evaluation
Report
03/11/2015
Corrective Action
Documents
CR-PLP-2020-
295
During Walkdown of EDG 1-1 Noted that Flexible Piping for
Crankcase Exhaust Motors was Degrading
04/23/2020
CR-PLP-2020-
01381
While Performing Maintenance in the Aux Feed Pump
Room, I&C Technicians Noticed Water Running Down the
Wall
04/30/2020
CR-PLP-2020-
01418
1-1 Diesel Generator Found that the Number 7L Petcock
was Spinning Freely When he Attempted to Open it
05/04/2020
CR-PLP-2020-
01806
Received EK-1319, Safety Injection Tank T-82B Hi-Lo Level
Unexpectedly
06/05/2020
CR-PLP-2020-
01861
MO-3045, Safety Injection Tank T-82B Outlet Isolation Valve
06/10/2020
CR-PLP-2020-
01883
PT-0510, Turbine Bypass Valve Controller Pressure for
CV-0511 Turbine Bypass Valve
06/11/2020
CR-PLP-2020-
01884
P-8D Diesel Driven Aux Feedwater Pump
06/11/2020
CR-PLP-2020-
01911
Nitrogen Station 5 Bottle Station has a Leak Somewhere
Causing Lowering Station Pressure
06/15/2020
CR-PLP-2020-
01915
PI-3027 HP Air to CV-3027 Actuator is Reading 192 psig,
eSOMS Limit is 190 psig
06/15/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR-PLP-2020-
01916
Observed Water Leaking from Overhead Drain Header Line
06/15/2020
Corrective Action
Documents
Resulting from
Inspection
CR-PLP-2020-
01969
NRC Inspector Noted a Discrepancy Between In-Plant
Labeling and a Table in SOP-3 Attachment 18.
06/22/2020
Procedures
SOP-3,
18
Engineered Safeguard Administrative Control Verification
Revision 106
Corrective Action
Documents
CR-PLP-2020-
01406
Fire Protection Check Sheet Annual Inspection Sticker was
Past Due
05/03/2020
CR-PLP-2020-
01869
P-8D, Diesel Driven Aux Feedwater Pump
06/10/2020
Fire Plans
Pre-Fire Plan 1
Control Room Elev 625'
Revision 5
71111.11Q Procedures
PSLEG-LOR-
TG Synch Scenario
Revision 2
Corrective Action
Documents
CR-PLP-2019-
0152
Received Alarm EK-0748, Reactor Water Low Level
Indication LIA-0105 Alarm
01/11/2019
CR-PLP-2020-
00032
CA-03 Maintenance Rule (a)(1) Evaluation Component
Failure Performance Criteria Exceeded on PCS/PZR
Instrumentation
01/28/2020
CR-PLP-2020-
01148
Water and Oil Mixture on the Floor of SFP Heat Exchanger
Room
04/11/2020
CR-PLP-2020-
01155
P-67A(LPSI Pump) has Boron Precipitate on Studs/Nuts at
Motor/Pump Interface
04/13/2020
CR-PLP-2020-
01176
CV-2056 Failure to Align to Clean Waste Receiver Tank
04/15/2020
CR-PLP-2020-
227
'A' Charging Pump Speed Elevated from Previous
Indications During CVCS Double Charging and Letdown
04/18/2020
CR-PLP-2020-
01320
Thermal Margin Monitor (TMM) PY-0102C Repeat
Functional Failure
04/27/2020
CR-PLP-2020-
01400
Time Displayed on the Three Recently Replaced LCD
Thermal Margin Monitor Screens (B/C/D) is One Hour Later
than Actual Time
05/02/2020
Corrective Action
Documents
CR-PLP-2020-
01937
Chemical & Volume Control System (CVC-CVC) has
Exceeded its Maintenance Rule Reliability Performance
Criteria
06/17/2020
Miscellaneous
PZR System Health Report 2Q2018
04/01/2018 -
06/30/2019
PZR System Health Report 4Q2018
10/01/2018 -
2/31/2018
PZR System Health Report 2Q2019
04/01/2019 -
06/30/2019
PZR System Health Report 4Q2019
10/01/2019 -
2/31/2019
PCS System Health Report 2Q2019
04/01/2019 -
06/30/2019
PCS System Health Report 2Q2018
04/01/2018 -
06/30/2018
PCS System Health Report 4Q2018
10/01/2018 -
2/31/2018
PCS System Health Report 4Q2019
04/01/2019 -
06/30/2019
WT-WTPLP-
2017-00011
CA-81 Proposed New Maintenance Rule Functional Failure
Performance Criteria for Primary Coolant System
Instruments
08/11/2017
Corrective Action
Documents
CR-PLP-2020-
264
Steam Leak Identified on CV-0711 Feed Pump P-1A
Recirculation
04/22/2020
CR-PLP-2020-
01522
Integrated Risk for RI-95B, Aux Feedwater Flow FT-0749
Instrument Loop Calibration was Reclassified on the Day of
Execution
05/12/2020
Drawings
M-202
Chemical & Volume Control System Piping & Instrument
Diagram
Revision 62
M-207
Feedwater & Condensate System Piping & Instrument
Diagram
Revision 53
Miscellaneous
Adverse
Condition and
Monitoring Plan
for WO 543553
CV-0711, Feed Pump P-1A Recirculation, Steam Leak
04/22/2020
Corrective Action
CR-PLP-2017-
Service Water System Tornado Missile Nonconformance
03/29/2017
Documents
248
Issue
CR-PLP-2017-
249
Fuel Oil System Tornado Missile Nonconformance Issue
03/29/2017
CR-PLP-2017-
250
Emergency Diesel Generator Tornado Missile
Nonconformance Issue
03/29/2017
CR-PLP-2017-
251
Control Room Ventilation System Tornado Missile
Nonconformance Issue
03/29/2017
CR-PLP-2017-
252
Steam Driven Auxiliary Feedwater Pump Tornado Missile
Nonconformance Issue
03/29/2017
CR-PLP-2017-
252
Component Cooling Water System Tornado Missile
Nonconformance Issue
03/29/2017
CR-PLP-2018-
00556
Additional Component Cooling Water System Tornado
Missile Vulnerability
01/31/2018
CR-PLP-2020-
00740
Thermal Margin Monitor (TMM) Screen is Showing Double
Numbers on Top of Each Other
03/04/2020
CR-PLP-2020-
242
Operability of the Class EC-2 Piping
04/20/2020
CR-PLP-2020-
2077
Small Packing Leak from CV-1656
06/29/2020
Engineering
Changes
Tornado Missile Nonconformance Review
01/29/2020
Miscellaneous
Integrated Plant Safety Assessment Systematic Evaluation
Program Palisades Plant
10/01/1982
Supplement 1
Integrated Plant Safety Assessment Systematic Evaluation
Program Palisades Plant
11/01/1983
Safety Evaluation Report Related to the full-term Operating
License for Palisades Nuclear Plant
11/01/1990
Operability
Evaluations
CR-PLP-2020-
01988
Pressurizer Heater Friction Block Operability Evaluation
06/23/2020
Procedures
QI-25
Thermal Margin Monitor Constant Checks
03/05/2020
Work Orders
00531075
PY-0102D; Replace Components and Reset Error Code 75,
QI-25
10/10/2019
00540421-01
PY-0102A; Replace Video Card and Other Components as
Needed
03/16/2020
Corrective Action
Documents
CR-PLP-2020-
01118
Received Alarm EK-0545 Preferred AC Bus No. 2
Unexpectedly
04/08/2020
Operability
Evaluations
Licensing Basis Document Change Process
Revision 19
Procedures
Process Applicability Determination
Revision 29
Work Orders
00541712
CV-0944A Install Packing Follower Temp Block
04/06/2020
Corrective Action
Documents
CR-PLP-2020-
248
Y-Phase Pole on Breaker 52-2624 (Condensing Unit VC-10
for Air Handling Unit V-96) Failed Instantaneous Overcurrent
Testing
04/21/2020
CR-PLP-2020-
275
During Inspection of PO-1712 (Modulating Damper D-21
Positioner), Electricians Observed that the Locking Nuts and
Feedback Arm were Loose on the Shaft
04/22/2020
Engineering
Changes
Temporary Leak Repair of the Pressure-Seal Body-to-
Bonnet Joint on Main Feedwater Pump (P-1A) Recirculation
Valve CV-0711
04/28/2020
Miscellaneous
Field Change
Request 86817
Installation Adjustments for EC-86710 Temporary Leak
Repair of the Pressure-Seal Body-to-Bonnet Joint on Main
Feedwater Pump (P-1A) Recirculation Valve CV-0711
Revision 0
Procedures
MO-33
Control Room Ventilation Emergency Operation
04/22/2020
Work Orders
0052856686
04/21/2020
00534222-03
3Y-8; New HGA Relay for VC-10 PMT
04/21/2020
00543553-01
CV-0711 - P-1A Recirc Valve
04/28/2020
00543843-02
05/06/2020
Corrective Action
Documents
CR-PLP-2020-
247
Cylinder Exhaust Temperature for 9R Cylinder was Found
Low Out of Specification
04/21/2020
CR-PLP-2020-
280
Relay for High Pressure Safety Injection (HPSI) P-66A
Protection was Found to Have its High Dropout, Dropout
Low
04/22/2020
CR-PLP-2020-
01970
SPI Control Rod Position Indication
06/22/2020
Procedures
MO-7A-2
Emergency Diesel Generator 1-2
04/21/2020
QI-3
Reactor Protection Matrix Logic Tests
Revision 7
QO-42
Inservice Testing of Shutdown Cooling Control Valves
Revision 24
QO-42
11
Mode 1, 2, or 3 (Greater than 325°F) Valve Exercising
Stroke Time Data Sheet
06/10/2020
Work Orders
0052910968-01
MO-7A-2 Emergency Diesel Generator 1-2 (K6B)
04/06/2020
0052925885-01
QO-42 IST Shutdown Cooling Valves
06/10/2020
Corrective Action
CR-PLP-2019-
PortaCount Suspicious Fit Factor Warning Received
03/19/2019
Documents
01160
Miscellaneous
FPF-GET-RPT
2
MSA Powered Air Purifying Respirator Practical
Revision 29
MED FPEX-MED-
PHYRSP
Respirator Medical Evaluation Records for Various
Individuals
Various
Dates
N/A
Posi3 USB Test Results for Scott Air-Paks 0867 and 1681
09/04/2019
N/A
Posi3 USB Test Results for Scott Air-Pak 1685
09/05/2019
PL-TRN19-2924
SCBA Practical and Fit Test
2/13/2019
PL-TRN20-0563
SCBA Practical and Fit Test
04/07/2020
PL-TRN20-0570
SCBA Practical and Fit Test
04/07/2020
PLLP-FBT-
SCOTTSCBA75
Training for Scott Air-Pak Self Contained Breathing
Apparatus
Revision 06
WI-RSD-T-008
SCBA Inspection Log
03/13/2020
Procedures
Inspection and Maintenance of Respiratory Protection
Equipment
Revision 10
PortaCount Respirator Fit Testing
Revision 07
Radiation Work
Permits (RWPs)
20190310
Forced Outage Containment Decontamination Activities
Revision 00
20190318
Pressurizer Spray Valve CV-1057 Maintenance
Revision 02
Work Orders
2906597
B5B SCBA Breathing Air Systems
2/20/2020
2907638
Respiratory Protection Equipment Inspection
04/09/2020
Corrective Action
Documents
CR-PLP-2019-
00857
Dose Rate Alarm During Charging Pump Work
2/27/2019
Corrective Action
Documents
Resulting from
Inspection
CR-HQN-2020-
01009
EN-RP-206 Potential Causes for Dosimetry Discrepancies
High-E Code Value Low
05/11/2020
CR-PLP-2020-
01517
Dosimetry Discrepancies and Ag-110m
05/12/2020
Miscellaneous
9.3
Dosimetry Investigation Report for Various Individuals
2/27/2020
PLP-RPT-19-009
Update to TID 2015-008 rev 5, Palisades Dosimetry
Background Performance
Revision 0
Procedures
Area Monitoring Program
Revision 1
Work Orders
2814864
TLD Monitoring Program
04/01/2019
71151
Corrective Action
Documents
CR-PLP-2020-
01041
The Monthly Performance Indicator (PI) for Critical Scope
Survival and Schedule Completion Changed from Green to
Red for the Month of March 2020
04/01/2020
Miscellaneous
4Q2019 NRC Performance Indicators
10/01/2019 -
2/31/2019
3Q2019 NRC Performance Indicators
07/01/2019 -
09/30/2019
2Q2019 NRC Performance Indicators
04/01/2019 -
06/30/2019
1Q2020 NRC Indicator Safety System Functional Failures
01/01/2020 -
03/31/2020
4Q2019 NRC Indicator Safety System Functional Failures
10/01/2019 -
2/31/2019
3Q2019 NRC Indicator Safety System Functional Failures
07/01/2019 -
09/31/2019
2Q2019 NRC Indicator Safety System Functional Failures
04/01/2019 -
06/30/2019
1Q2020 NRC Performance Indicators
01/01/2020 -
03/31/2020
Corrective Action
Documents
CR-PLP-2019-
03474
Inadvertent Water Transfer from SFP to SIRWT
09/05/2019
CR-PLP-2020-
00611
RV-2006 Lifted Unexpectedly During Plant Evolution
04/14/2020
CR-PLP-2020-
00696
Palisades Oversight of Switchyard Activities
03/02/2020
CR-PLP-2020-
284
Received Alarm EK-0704, Letdown Heat Exch Tube Inlet Hi-
Lo Press Unexpectedly
04/22/2020
CR-PLP-2020-
01314
Received EK-0704, Letdown Heat Exch Tube Hi-Lo Press
Momentarily While Lowering Charging Letdown per SOP-2A
04/26/2020
CR-PLP-2020-
01818
The PPC Shows a Declining Tave Trend on the "8 Hour"
and "Day" Trend Time Frames
06/06/2020
CR-PLP-2020-
01938
Quench Tk Level and Pressure Along with a Rise in
Temperature on RV-2006 Intermediate Letdown Relief Valve
06/17/2020
CR-PLP-2020-
01950
On 06/04/2020 Quench Tank Pressure Started Rising at a
Rate of Approximately 1.2 psig/day
06/17/2020
Miscellaneous
DPRM/APRM Report
2/2020
DPRM/APRM Report
11/2019
Procedures
Corrective Action Program
Revision 40
Casual Analysis Process
Revision 31
Work Orders
0052910968-01
MO-7A-2 Emergency Diesel Generator 1-2 (K-6B)
04/06/2020