IR 05000255/2020010
| ML20237F480 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/24/2020 |
| From: | April Nguyen NRC/RGN-III/DRP/B2 |
| To: | Corbin D Entergy Nuclear Operations |
| References | |
| IR 2020010 | |
| Download: ML20237F480 (17) | |
Text
August 24, 2020
SUBJECT:
PALISADES NUCLEAR PLANT - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000255/2020010
Dear Mr. Corbin:
On July 10, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Palisades Nuclear Plant and discussed the results of this inspection with yourself and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspection team reviewed the stations corrective action program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for corrective action programs. Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments.
Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment, and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews the team found no evidence of challenges to your organizations safety-conscious work environment. Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
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 by Hironori Peterson for/
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-2020-010-0036
Licensee:
Entergy Nuclear Operations, Inc.
Facility:
Palisades Nuclear Plant
Location:
Covert, Michigan
Inspection Dates:
June 22, 2020 to July 10, 2020
Inspectors:
P. Laflamme, Senior Resident Inspector
V. Meghani, Reactor Inspector
J. Neurauter, Senior Reactor Inspector
R. Ruiz, Project Engineer
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 a biennial problem identification and resolution 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
None.
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), regional inspectors were directed to begin telework. The inspection documented below was determined that the objectives and requirements stated in the IP, in part, could be performed remotely.
OTHER ACTIVITIES - BASELINE
71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 02.04)
- (1) The inspectors performed a biennial assessment of the licensees corrective action program, use of operating experience, self-assessments and audits, and safety conscious work environment.
- Corrective Action Program Effectiveness: The inspectors assessed the corrective action programs effectiveness in identifying, prioritizing, evaluating, and correcting problems. The inspectors also conducted a five-year review of the component cooling water system.
- Operating Experience, Self-Assessments and Audits: The inspectors assessed the effectiveness of the stations processes for use of operating experience, audits and self-assessments.
- Safety Conscious Work Environment: The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.
INSPECTION RESULTS
Assessment 71152B Assessment of the Corrective Action Program
Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
Effectiveness of Problem Identification
Overall, the station was effective at identifying issues at a low threshold and was properly entering them into the corrective action program (CAP) as required by station procedures.
The team determined that the station was generally effective at identifying negative trends that could potentially impact nuclear safety. The team walked down the emergency diesel generators and various security-related areas. For the areas reviewed, the team did not identify any issues in the area of problem identification.
Effectiveness of Prioritization and Evaluation of Issues
In-depth reviews of a risk-informed sampling of condition reports (CRs), work orders (WOs),and cause evaluations were completed, including a 5-year time period for the component cooling water (CCW) system. The team determined that the licensee had established a low threshold for entering deficiencies into the CAP, that the issues were generally being appropriately prioritized and evaluated for resolution, and that corrective actions (CAs) were implemented to mitigate the future risk of issues occurring that could affect overall system operability and/or reliability.
The team identified one example of a CR categorized as N (non-adverse) where the team considered the issue to be a condition adverse to quality (CAQ). Specifically, CR-PLP-2018-03582 documented microbiologically induced corrosion (MIC) of the safety-related train B CCW system heat exchanger, E54B, with a loss of pressure boundary material of more than 1/3rd of the nominal wall thickness at the south end-bell of the heat exchanger.
Although the condition was bounded by a previously evaluated condition on the E54A heat exchanger, the team considered this to be a deviation or deficiency, i.e., a departure from the normal standard, because the wall thickness was reduced below the specified thickness by more than the standard allowable-tolerances and therefore met the definition of a CAQ in procedure EN-LI-102. The plant staff determined that the condition of the E54B heat exchanger was acceptable for at least 52 months because it was bounded by an evaluation of E54A heat exchanger. The bounding structural integrity evaluation was documented in CR-PLP-2018-01375, which concluded that E54A condition was acceptable for an interval of 52 months and that a follow-on examination would be required no later than 26 months. The team noted that although the E54A evaluation was used as the basis for acceptance of the E54B condition, no actions were identified for subsequent examination of the E54B. The team concluded that the licensee's "non-adverse" CR classification was incorrect, but did not have any safety concerns or issues with the licensee's operability determination, so the issue was considered minor in nature.
Effectiveness of Corrective Actions
The team concluded that the licensee was generally effective in developing CAs that were appropriately focused to correct the identified problem and to address the root and contributing causes for significant conditions adverse to quality to preclude repetition. The licensee generally completed CAs in a timely manner and in accordance with procedural requirements commensurate with the safety significance of the issue. For NRC-identified issues, the team determined that the licensee generally assigned CAs that were effective and timely.
Assessment 71152B Assessment of Operating Experience and Self-Assessments and Audits
Based on the samples reviewed, the team determined that licensee performance in the use of Operating Experience (OE) and Self-Assessments and Audits adequately supported nuclear safety.
Use of Operating Experience
The licensee routinely screened industry and NRC OE information for station applicability.
Based on these initial screenings, the licensee initiated actions in the CAP to fully evaluate the impact, if any, to the station. When applicable, actions were developed and implemented in a timely manner to prevent similar issues from occurring. Operating Experience lessons-learned were communicated and incorporated into plant operations.
Self-Assessments and Audits
The inspectors reviewed several audits and self-assessments and deemed those sampled as thorough and intrusive with regards to following up with the issues that were identified through previous NRC inspections and in the self-assessments and fleet oversight audits.
Reviewed corrective actions for the identified issues were deemed reasonable and completed commensurate with their safety significance. The inspectors regarded licensee performance as adequately self-critical of their own performance and that performance-related issues were being identified through their self-assessment process.
Assessment 71152B Assessment of Safety Conscious Work Environment
The team reviewed the stations programs to establish and maintain a safety-conscious work environment and interviewed over 30 station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews, workers at the station expressed freedom to raise and enter safety concerns through any one of the various avenues available to them, and the team encountered no indications of chilling or retaliation. Finally, all plant personnel interviewed were aware of the Employee Concerns Program and expressed a willingness to use it as an avenue to raise concerns, if desired.
In addition, the team included questions on the topic of the permanent plant shutdown (scheduled for 2022) to assess for any negative impacts on safety performance or overall safety culture both for the individuals and the organization. Employees consistently communicated the belief that sufficient competency, engagement, resources, and commitment exist at the station to maintain high performance standards at the site.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On July 10, 2020, the inspectors presented the biennial problem identification and resolution inspection results to Mr. D. Corbin, Vice President, Operations and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-PLP-2019-
03474 NCA
Line of Sight for CR-PLP-2019-03474
11/04/2019
OE-NOE-2018-
00012
NRC-RIS-2005-31 - R1 Control of Security Related Sensitive
Unclassified Non-safeguards
01/04/2018
CR-PLP-2015-
00180
P-52C CCW Pump Oil Leak
01/12/2015
CR-PLP-2016-
03486
p-52B CCW Pump Oil Leak
07/28/2016
CR-PLP-2017-
2568
P-52C CCW Pump Leaking Oil
05/16/2017
CR-PLP-2017-
05551
CV-2008 PMU TANK T-81 M/U Not Able to Be Manually
Stroked
2/07/2017
CR-PLP-2018-
00405
Various Attachments in (3) Three Radiation Work Permit
Packages Found with Incomplete Information
01/23/2018
CR-PLP-2018-
00469
Approved and Routed Preventative Maintenance Change
Request 251063 Not Implemented
01/26/2018
CR-PLP-2018-
01126
Some of Posting Formats (Colors, Specific Wording, Etc.) in
Fleet Procedure EN-RP-108, "Radiation Protection Posting,
Differ from Postings Currently Used and at Palisades
03/07/2018
CR-PLP-2018-
01523
Equipment Failure Evaluation: PS-0139A did not Respond to
Flow
05/22/2018
CR-PLP-2018-
01691
T-105C, Charging Pump P-55C Suction Stabilizer "As
Found" Bladder Pressure at ZERO PSI
04/05/2018
CR-PLP-2018-
01961
RAS Pump Air Sampler Number 233 Not in Sentinel
Database with Current Calibration
04/23/2018
CR-PLP-2018-
2110
During QO-1 "Safety Injection System," Right Channel Safety
Injection Actuated Red Light on Control Room Panel C-13
Failed to Illuminate
05/02/2018
CR-PLP-2018-
2129
No Station or Fleet Level Procedural Guidance Exists that
Directs Site Emergency Planning (EP) Staff to Submit Annual
Letter Regarding Interface Adequacy (as required by 10 CFR
50.54(t)(2)) into Records
05/03/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR-PLP-2018-
2143
During Trouble Shooting for CR-PLP-2018-02110
Discovered Wire #13 Not Landed on SIS-2
05/03/2018
CR-PLP-2018-
2143
Right Channel Safety Injection System Wire Not Landed on
SIS-2 Relay
05/03/2018
CR-PLP-2018-
2143 CA-3
Root Cause Evaluation: Wire Not Landed on the Maintained
Safety Injection Initiation Relay Circuit
06/18/2018
CR-PLP-2018-
2518
NIOS Identified - Emergency Preparedness Job Aids
05/24/2018
CR-PLP-2018-
2568
Regulatory Assurance - NRC Compliance Closure Review of
05/29/2018
CR-PLP-2018-
2571
Maintenance and Technical Training Comprehensive
Assessment Negative Observation
05/29/2018
CR-PLP-2018-
2578
Concurrent Verification May Not Be Appropriate for Technical
Specification Surveillance Procedure RO-12, Containment
High Pressure (CHP) and Spray System Tests, Step 5.8.27
05/29/2018
CR-PLP-2018-
2794
Some Fire Extinguishers at the Emergency Operations
Facility (EOF) have not been Serviced or Inspected Since
2015
06/11/2018
CR-PLP-2018-
2980
Multiple Leaks Detected during PMT of P-52C CCW Pump
06/21/2018
CR-PLP-2018-
03393
Simulator Evaluation Guide Issues
CR-PLP-2018-
03582
E-54B CCW Heat Exchanger Wall Thickness Below
Minimum
08/02/2018
CR-PLP-2018-
03989
Error in Record "COG-0118" - Monthly Condenser Off-gas
Effluent Calculation
08/30/2018
CR-PLP-2018-
04632
Palisades SRC 2018-02 Noteworthy Observation
10/10/2018
CR-PLP-2018-
04917
Piece of Metal Found Near P-52A CCW Pump
10/20/2018
CR-PLP-2018-
05329
VT-3 Examination of Piping Support H-19 Identified Contact
between Spring can Support and Adjacent Metal Plate
11/01/2018
CR-PLP-2018-
Regulatory Assurance - NRC Compliance Closure Review of
11/02/2018
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
05405
CR-PLP-2018-
05830
Erratic indications CV-0944A during RT-8D
11/10/2018
CR-PLP-2018-
06329
ICS 3000 Out of Service for Sulfate Analysis
11/26/2018
CR-PLP-2019-
00063
CRDM Housing #37 & #28 Cooling Lines
01/04/2019
CR-PLP-2019-
222
Failed Power Supply for P/S-0712 Not Sent Out for Timely
Failure Evaluation
03/25/2019
CR-PLP-2019-
00314
P-52B CCW Pump Degraded Trend
01/21/2019
CR-PLP-2019-
00327
Recurring Equipment Failures on Control Room Ventilation
System, Maintenance Rule Functional Failures
01/22/2019
CR-PLP-2019-
00327 CA-1
Non-adverse Condition Analysis: Recurring Equipment
Failures on Control Room Ventilation System
03/06/2019
CR-PLP-2019-
00655
Search of Adverse CRs using Trend Code EX11 for the Last
Months
2/11/2019
CR-PLP-2019-
00918
Current Calibration Record for WP2-1050 Protean Serial
Number 1171115 and PM-7 Serial Number 688 Could Not
Be Located in Records
03/05/2019
CR-PLP-2019-
01400
Annual Radiological Effluent Release Reports (ARERR)
Misidentified Reactor Type
04/05/2019
CR-PLP-2019-
01534
ERO Team Failed to Correctly Determine the Status of a
Radiological Release
04/16/2019
CR-PLP-2019-
01537
During the Performance of the Palisades Emergency
Planning Full Scale Drill, April 10th, 2019, the EOF Dose
Assessment Team made Several Errors that could have
Impacted the Performance of the ERO
04/16/2019
CR-PLP-2019-
01543
Drill and Exercise Performance (DEP) Data Indicates
Presence of an Aggregate Performance Issue
04/17/2019
CR-PLP-2019-
2089
OSC & TSC Players Showed up to the Facility without DLR.
ERO Players Needs to Validate they have DLR Assigned
05/22/2019
CR-PLP-2019-
2118
During the Performance of the Palisades Emergency
Planning Full Scale Drill, May 22, 2019, the Dispatch of
05/23/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Damage Control Teams in a Timely Manner Needs to be
Improved
CR-PLP-2019-
22 CA-1
Adverse Condition Analysis: Delay in Obtaining Auxiliary
Feedwater Actuation System (AFAS) Power Supply Failure
Evaluation
05/09/2019
CR-PLP-2019-
2855
Evaluation for CR-PLP-2018-2699 was too Narrowly
Focused
09/10/2019
CR-PLP-2019-
03005
CV-1057 Rework Due to Step 5.2.30 of Section 5.2, VALVE
REPACK, of Procedure PCS-M-8 Not Revised
07/30/2019
CR-PLP-2019-
273
Monthly Groundwater Sampling Results Contain Unexpected
Tritium Indications in Monitoring Well Sample
08/20/2019
CR-PLP-2019-
03609
Viper 20 Valve Diagnostic Testing System) Found to Be Non-
Conforming during Calibration Services
09/11/2019
CR-PLP-2019-
03692
NRC EQ DBAI: Evaluation of Effects of pre-RAS Borated
Containment Spray on Specific Materials in EQ Qualified
Equipment Exposed to Spray is not Provided in EQ Program
Documentation as Required by 10 CFR 50.49(e)(3)
09/16/2019
CR-PLP-2019-
03806
Spare Cathode Ray Tube Chassis Serial/Number-013 for
TMM's Failed on Bench
09/23/2019
CR-PLP-2019-
03819
TMM Stock Monitor Circuit Board Installed 180 Degrees Out
of Position
09/23/2019
CR-PLP-2019-
03819
TMM Stock Monitor Circuit Board Installed 180 Degrees Out
of Position
09/23/2019
CR-PLP-2019-
03829
Foreign Material Exclusion (FME) Requirements Contained
in Chemistry and Maintenance Procedures Not Consistently
Followed
09/24/2019
CR-PLP-2019-
03829 CA-1
Adverse Condition Analysis: Foreign Material Exclusion
(FME) Requirements Contained in Chemistry and
Maintenance Procedures Not Consistently Followed
10/24/2019
CR-PLP-2019-
228
The licensee Failed to Base the Qualification of Electric
Equipment Inside Containment on a Chemical Composition
that was at Least as Severe as that Resulting from the most
10/22/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Limiting Mode of Plant Operation
CR-PLP-2019-
04558
Nuclear Independent Oversight (NIOS) identified - Problem
Identified during the Performance of Observation O2C-PLP-
2019111448
11/14/2019
CR-PLP-2019-
04605
Mechanics during the EP Drill Conducted on November 13,
2019, Simulated Working (coupling assembly) on
Containment Spray Pump P-54B without Simulating being
Signed onto a Tagout or using EN-OP-200
11/19/2019
CR-PLP-2020-
238
Cyclic Status Control Performance
03/16/2020
CR-PLP-2020-
00338
As-Found PS-1482 and PS-1498 (K-6A Jacket Water
Pressure Switches) Out of Tolerance in Conservative
Direction
2/04/2020
CR-PLP-2020-
00402
Department Aggregate Performance Issue (API) Identified
2/07/2020
CR-PLP-2020-
00510
CV-0944A, CCW to SFP HXS failed to close during QO-1
2/17/2020
CR-PLP-2020-
00513
Sample Point for Service Water Grab for MR-36, when
Service Water Compositor Is Out of Service
2/18/2020
CR-PLP-2020-
00596
Two Additional Deficiencies were Identified in the Inform
Program Related to the Generation of Technical Data Sheets
2/24/2020
CR-PLP-2020-
00618
Procedure FPS-E-1 Incorporated Non "AS-BUILT" /
"PENDING" DRN 16-P460
2/25/2020
CR-PLP-2020-
00884
Issue Related to Sensitivity Test of Gamma Portal Monitors
to Detect Intakes of Contamination
03/18/2020
CR-PLP-2020-
00981
Boric Acid Leak - P-66B High Pressure Safety Injection
Pump
03/25/2020
CR-PLP-2020-
00988
CV-0944A not Fully Closed on Manual Operation
03/26/2020
CR-PLP-2020-
01053
Document Errors Found during EC-86037
04/02/2020
CR-PLP-2020-
01167
Administrative Limit for Service Water Total Residual Oxide
Exceeded
04/14/2020
CR-PLP-2020-
Condition Report Documents Request for Release and
04/14/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
01174
Installation of Non-conformant Material
CR-PLP-2020-
01184
Suspected Bad Female End Connection Point to Mettler
ToledoT-90 Boron Auto Titrator pH Probe
05/19/2020
CR-PLP-2020-
01195
AMS4 Did Not Have Filter Paper in Detector
04/16/2020
CR-PLP-2020-
212
Radiation Work Permit (RWP) Packages with Attention to
Detail Errors
04/17/2020
CR-PLP-2020-
220
RP Supervisor Does Not Have Required Training to Meet
Requirements in EN-OM-123, Fatigue Management Program
04/17/2020
CR-PLP-2020-
01305
ICP-OES Tripping on High Temperature Reading
05/20/2020
CR-PLP-2020-
01392
Measuring &Testing Equipment ID# 006428 (OD
MICROMETER) Found Non-conforming during Calibration
Services
05/01/2020
CR-PLP-2020-
01446
Inadequate or Untimely Response to C-42 Secondary Panel
Slarms and Deficient Chemistry Parameters Does Not Meet
Management Expectations
05/05/2020
CR-PLP-2020-
01448
PCS Lithium Under Target at 2.06 ppm Post Delithiation
05/06/2020
CR-PLP-2020-
01457
Area of Concern Associated Rigorous Use of HU/THINK 3
Tools
05/06/2020
CR-PLP-2020-
01460
Radiation Protection Department Aggregate Performance
Issue
06/22/2020
CR-PLP-2020-
01468
Measuring &Testing Equipment ID#014993 (Dynamometer)
Found Non-conforming during Calibration Services
05/07/2020
CR-PLP-2020-
01517
Dosimetry Investigation Reports (DIRs) May Not Accurately
Characterize Impact of Silver-110m on Dosimetry Results
05/12/2020
CR-PLP-2020-
01521
Contrary to EN-EV-112, Unlabeled, Unattended, Open
Five-Gallon Bucket Containing Approximately Two Gallons of
Apparent Aluminum Sulfate
05/12/2020
CR-PLP-2020-
01533
PMT of Newly Installed Mag Traps on Secondary Sample
Panel, Noted Operation of Mag Traps Causes EC-42
Dissolved Oxygen Alarms
05/13/2020
CR-PLP-2020-
Measuring &Testing Equipment ID#012344 (15-75 Inch Dial
05/15/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
01572
Torque Wrench) Found Out of Tolerance during Calibration
Services
OE-NOE-2018-
00012
NRC-RIS-2005-31 - R1
01/04/2018
OE-NOE-2018-
00042
T.S. 3.0.4 - MODE CHANGES MADE WITH INOPERABLE
EQUIPMENT TS LCO 3 0 4 June 2015 to September 2017
01/17/2018
OE-NOE-2019-
00142
INPO-IER-L3-19-5 - Crew Leadership Shortfalls Result in
Nonadherence to Procedure-required Reactor Scram and
Reactivity Transient
05/08/2019
OE-NOE-2020-
00068
IRIS-470127 - Emergency Diesel Generators Autostarted as
Designed Due to Loss of Power To 6.9kV Shutdown Board
03/16/2020
Miscellaneous
Q4-2019 CCS
System Health
report
Q4-2019 CCS System Health report
05/26/2020
QA-7-2018-PLP-1 QA Audit - Emergency Preparedness [10CFR50.54 (t)]
06/11/2018
QA-8-2019-PLP-1 Engineering Programs (Engineering, License Renewal, and
Operational Information Technology) 2019 Audit Report
05/14/2019
Procedures
Corrective Action Program
Self-Assessment and Benchmark Process
Cause Analysis Process
On-line Work Management Process
Self-Assessments LO-PLPLO-2018-
00001
Chemistry Human Performance Assessment
4/25/2018
LO-PLPLO-2018-
00017
Maintenance - Adherence to Electrical Safety Practices
10/17/2018
LO-PLPLO-2018-
00023
Chemistry 4th Quarter 2018 Chemistry Tracking
03/14/2019
LO-PLPLO-2018-
00053
Failed Fuel Airborne Radioactivity Controls Formal
Benchmark
06/05/2018
LO-PLPLO-2018-
00067
Effectiveness Review for RCE, CR-PLP-2018-02143
05/07/2018
LO-PLPLO-2019-
00014
Pre-NRC Design Basis Assurance Inspection (DBAI)
Self-Assessment
09/05/2019
LO-PLPLO-2019-
2019 Pre-NRC Emergency Planning Program Inspection
2/11/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
00026
Assessment
LO-PLPLO-2019-
00049
20 PI&R Readiness Assessment
03/24/2020
QA-10-2018-PLP-
Quality Assurance Audit Report: Maintenance
08/07/2018
QA-14-15-2019-
PLP-1
Quality Assurance Audit Report: Combined Radiation
Protection (RP) and Radwaste (RW)
10/29/2019
QA-2-6-2019-
PLP-1
Quality Assurance Audit Report: Combined Chemistry,
Effluents and Environmental Monitoring
09/30/2019
Work Orders
00528935-01
LT-0146B (PCP-50D) Upper Oil Level Indicates High Off
Scale
00541047-01
CV-0605; Heater E-6B Drain Valve Not Controlling Level
2924271-01
Manual Stroke of Valve CV-2008/2010
0