IR 05000255/2020003
| ML20318A040 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 11/13/2020 |
| From: | Billy Dickson NRC/RGN-III/DRP/B2 |
| To: | Corbin D Entergy Nuclear Operations |
| References | |
| IR 2020003 | |
| Download: ML20318A040 (18) | |
Text
November 13, 2020
SUBJECT:
PALISADES NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000255/2020003
Dear Mr. Corbin:
On September 30, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palisades Nuclear Plant. On October 28, 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 License No. DPR-20
Enclosure:
As stated
Inspection Report
Docket Number:
05000255
License Number:
Report Number:
Enterprise Identifier: I-2020-003-0031
Licensee:
Entergy Nuclear Operations, Inc.
Facility:
Palisades Nuclear Plant
Location:
Covert, MI
Inspection Dates:
July 01, 2020 to September 30, 2020
Inspectors:
J. Benjamin, Senior Reactor Inspector
J. Bozga, Senior Reactor Inspector
E. Fernandez, Reactor Inspector
M. Holmberg, Senior Reactor Inspector
P. Laflamme, Senior Resident Inspector
J. Mancuso, Resident Inspector
V. Myers, Senior Health Physicist
C. St. Peters, 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
None.
PLANT STATUS
The plant began the inspection period at rated thermal power and remained at or near rated thermal power until August 5, 2020. On August 5, 2020, the plant began coast down until reaching approximately 88 percent power on August 30, 2020. On August 30, 2020, the plant was down powered and taken offline for a refueling outage. The plant remained offline 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
71111.04 - 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)1-2 emergency diesel generator (EDG) lube oil and jacket water cooling water system on July 6, 2020
- (2) Station battery number 1 on August 6, 2020
- (3) Spent fuel pool (SFP) cooling system on September 15, 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) South west penetration room on July 13, 2020
- (2) Cable spreading room on August 18, 2020 (3)1C 2.4kV switchgear room on August 24, 2020
- (4) Charging pump room on August 25, 2020
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) West engineering safeguards room on September 21, 2020
===71111.08P - Inservice Inspection Activities (PWR)
PWR Inservice Inspection Activities Sample (IP Section 03.01) (1 Partial)
(1)
(Partial)
The inspectors verified that the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from 08/31/2020 to 09/30/2020:
03.01.a - Nondestructive Examination and Welding Activities.
- Encoded Phased Array Ultrasonic Examination (PAUT) of SDC Safe End to Elbow Dissimilar Metal Weld. Component ID PCS-12-SDC-2H1-1
- Encoded Phased Array Ultrasonic Examination (PAUT) of SDC Safe End to Elbow Dissimilar Metal Weld. Component ID PCS-12-SDC-2H1-2
- Bare Metal Visual Exam (BMVT) of 1" Instrument Tap. Component ID PCS-042 Weld 6 "B Hot Leg"
- Bare Metal Visual Exam (BMVT) of 1" Instrument Tap. Component ID PCS-042 Weld 8 "B Hot Leg"
- Bare Metal Visual Exam (BMVT) of 1" Instrument Tap. Component ID PCS-042 Weld 10 "B Hot Leg"
03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities.
- Bare Metal Visuals (BMV) of 54 Penetrations on the Reactor Vessel Closure Head (RVCH)
- Ultrasonic Examination (UT) of 54 Penetrations on the Reactor Vessel Closure Head (RVCH)
- Half Nozzle Weld Repair of Penetrations 17 and 34, Work Order 00550825
03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.
- CR-PLP-2019-02918 Pressurizer Spray Valve from Loop 1A CV-1057
- CR-PLP-2019-04528 Flange downstream of MV-ES3418
- CR-PLP-2019-02059 Flange near HC4-H103 and Temporary Connection for SFP Cooling
03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities.
- Eddy current testing of 7,589 Tubes in steam generator (SG 1A) and 7753 Tubes in (SG 1B)
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)
=
- (1) The inspectors observed and evaluated licensed operator performance in the Control Room during reactor shutdown on August 30, 2020
- (2) The inspectors observed and evaluated licensed operator performance in the Control Room during reduced inventory on September 4, 2020
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated PSLEG-LOR-20C-01 on August 11, 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) Chemical and volume control system on July 10, 2020
- (2) Service water system on September 22, 2020
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Elevated risk for planned maintenance on component cooling water system and battery charger #4 on July 27, 2020
- (2) Elevated risk for planned maintenance on high pressure safety injection and containment spray systems on July 28, 2020
- (3) Elevated risk for a severe weather warning impacting the 2400V 1C startup transformer breaker maintenance activities on August 10, 2020
- (4) Shutdown risk assessment during reduced inventory on September 8, 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) Elevated Lake Michigan water level evaluation on July 21, 2020
- (2) CV-0826 cotter pin misalignment evaluation on July 28, 2020
- (3) Spalling of the concrete near containment vertical tendon V-140 anchorage on August 21, 2020
- (4) Elevated inverter #4 temperatures evaluation on August 24, 2020
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post maintenance test activities to verify system operability and functionality:
- (1) EDG 1-2 start test following PCV-1489 replacement on July 21, 2020
- (2) P-52 B component cooling water (CCW) baker testing on August 5, 2020
- (3) CV-0826 control valve testing on August 6, 2020
- (4) Core verification examination on September 25, 2020
- (5) Nuclear instrument source range testing on September 28, 2020
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Partial)
(1)
(Partial) The inspectors evaluated refueling outage 1R27 beginning August 30, 2020
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) QO-15B, P-52B component cooling water (CCW) pump test on July 30, 2020
- (2) RO-128-1, 1-1 EDG 24-hour load run test on August 8, 2020
- (3) Left train safety injection system test on August 18, 2020
- (4) RT-8C, engineering safeguards test on September 24, 2020
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) QO-19B - high pressure safety injection (HPSI) pump and emergency safety system check valve operability test, on July 15,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Radiological Hazard Assessment (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards
Instructions to Workers (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated radiological protection-related instructions to plant workers
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material:
- (1) The inspectors observed surveys of potentially contaminated material leaving the radiologically controlled are.
- (2) The inspectors observed workers exiting the radiologically controlled area
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities:
- (1) Reactor vessel disassembly under RWP 20200433
- (2) Scaffolding activities in containment under RWP 20200424
- (3) Steam generator primary side activities under RWP 20200454
High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (2 Samples)
The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:
- (1) Access to the reactor cavity, located inside containment
- (2) Area surrounding the regenerative heat exchanger, located inside containment
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
- (1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements
71124.02 - Occupational ALARA Planning and Controls
Implementation of ALARA and Radiological Work Controls (IP Section 03.03) (2 Samples)
The inspectors evaluated the licensees communication of as low as is reasonably achievable ALARA and radiological work controls for the following work activities:
- (1) Reactor vessel disassembly under RWP 20200433
- (2) Steam generator primary side activities under RWP 20200454
Radiation Worker Performance (IP Section 03.04) (1 Sample)
The inspectors evaluated radiation worker and radiation protection technician performance during:
- (1) Reactor vessel disassembly under RWP
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
MS07: High Pressure Injection Systems (IP Section 02.06)===
- (1) Unit 1 (July 1, 2018-June 30, 2020)
MS09: Residual Heat Removal Systems (IP Section 02.08) (1 Sample)
- (1) Unit 1 (July 1, 2018-June 30, 2020)
BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)
- (1) Unit 1 (July 1, 2018-June 30, 2020)
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On October 28, 2020, the inspectors presented the integrated inspection results to Mr. D. Corbin, Site Vice President, and other members of the licensee staff.
- On October 1, 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-
2120
Protected Equipment for 1-2 Emergency Diesel Generator
07/06/2020
CR-PLP-2020-
2126
Notification per MISO that Maintenance Activities Must be
Curtailed Due to Generation Availability Constraints
07/06/2020
CR-PLP-2020-
2149
During Performance of MO-7A-1, FI-0890, Diesel Generator
1-1 Service Water Flow was Reading 710gpm
07/08/2020
CR-PLP-2020-
298
VC-10 Suction Pressure Cycling From 52 psig to 58 psig on
PI-1676
07/21/2020
CR-PLP-2020-
2345
P-7B Service Water Pump Basket Strainer
07/25/2020
CR-PLP-2020-
2354
Corrosion Found During Rounds in Station Battery Number 2 07/26/2020
CR-PLP-2020-
2542
Induction Disc of the GE 12IAC53A101A Relay 151-106 X-
Phase was Stuck to the Backstop of the Time Dial/Lever
08/10/2020
Corrective Action
Documents
Resulting from
Inspection
CR-PLP-2020-
2129
NRC Identified the Floor Drain Cover on the South End of
the 1-2 Emergency Diesel Generator Ajar
07/06/2020
CR-PLP-2020-
2130
The NRC Identified that the 1-2 Emergency Diesel
Generator Vents are Dirty and may Require Cleaning
07/06/2020
CR-PLP-2020-
2131
NRC Identified a Potential Oil Leak on the North End of the
1-1 Emergency Diesel Generator
07/06/2020
CR-PLP-2020-
2329
NRC Identified There is Vegetation Growing on the North
and North East Sides of EX-17, Station Transformer 17
07/23/2020
CR-PLP-2020-
2330
NRC Identified Debris on the Floor of the 1-1 and 1-2 EDG
Rooms
07/23/2020
Drawings
M-221
Piping & Instrumentation Diagram, Spent Fuel Pool Cooling
System, Sheet 2
Miscellaneous
DBD 2.07
Design Basis Document for Spent Fuel Pool Cooling System
Procedures
Loss of Spent Fuel Pool Cooling
SOP-27
Fuel Pool System
Corrective Action
Documents
CR-PLP-2020-
2416
PI-5350A, Fire Protection System Header Pressure was
Trending Down
07/30/2020
Fire Plans
Pre-Fire Plan 13B Charging Pump Rooms / Elevation 590'
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Pre-Fire Plan 2
Cable Spreading Room; Elevation 607'
Pre-Fire Plan 26
Southwest Cable Penetration Room; Elevation 590' & 607'
Pre-Fire Plan 4
1-C Switchgear Room and Manhole 1, 2, & 3/Elevation 590'
Corrective Action
Documents
CR-PLP-2020-
2461
Expansion Joint XJ-0421 Flood Barrier on HB-23-3" was
Identified as Having a Slit in the Joint Approximately Midway
Down the Southern Side of the Joint
08/04/2020
Miscellaneous
DBD 7.08
Design Basis Document Plant Protection Against Flooding
Procedures
Internal Plant Flooding
Corrective Action
Documents
Resulting from
Inspection
CR-PLP-2020-
03380
Ultrasonic Data Analysis of a Relevant Indication on
Penetration 34 on the Reactor Vessel Head
09/11/2020
CR-PLP-2020-
03427
Ultrasonic Data Analysis of a Relevant Indication on
Penetration 17 on the Reactor Vessel Head
09/13/2020
Procedures
54-ISI-400-023
NONDESTRUCTIVE EXAMINATION PROCEDURE
Multi-Frequency Eddy Current Examination of SG Tubing
2/12/2018
54-ISI-619-000
Automated Ultrasonic Examination of Open Tube RPV
Closure Head Penetrations-Palisades Specific
07/30/2020
CEP-NDE-0955
Visual Examination (VE) of Bare-Metal Surfaces
307
LMT-10-PAUT-
007
Fully Encoded Phased Array Ultrasonic Examination of
Dissimilar Metal Piping Welds
SEP-BAC-PLP-
001
Boric Acid Corrosion Control Program Engineering Nuclear
Programs Applicable Sites
71111.11Q Miscellaneous
SES-405
LOR Simulator Exam Scenario
Procedures
GOP-14
Reduced Inventory Checklist
GOP-8
Power Reduction and Plant Shutdown to Mode 2 or Mode 3
= 525°F
Corrective Action
Documents
CR-PLP-2018-
05815
CV-0869, CAC VHX-4 SW Inlet, Valve Actuator Moved in the
Closed or Open Direction, but Valve Itself did not Move
11/09/2018
CR-PLP-2019-
04925
Baker Offline Motor Test Could not be Completed
2/16/2019
CR-PLP-2020-
2475
Discharge Accumulator for P-55C Charging Pump the "As
Found" Pressure of the Tank Bladder was 1287 psig
08/05/2020
CR-PLP-2020-
2476
Charging Pump "As Found" Pressure of the Tank Bladder
was 0.0 psig
08/05/2020
CR-PLP-2020-
Critical Service Water System (CSW) has Exceeded the
08/10/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2543
Near (a)(1) Threshold
CR-PLP-2020-
03184
Exceeded Maintenance Rule (MR) Performance Criteria
(PC) for Number of Functional Failures (#) in 24 Months for
the Main Steam System
09/07/2020
Miscellaneous
System Health
Report
Chemical & Volume Control System
2018
System Health
Report
Chemical & Volume Control System
2019
System Health
Report
CSW - Critical Service Water
Q2-2019
System Health
Report
CSW - Critical Service Water
Q2-2020
System Health
Report
CSW - Critical Service Water
Q4-2018
System Health
Report
CSW - Critical Service Water
Q4-2019
Corrective Action
Documents
CR-PLP-2020-
2421
Removed from Service to Clean BS-1318, P-7A Service
Water Pump Basket Strainer
07/31/2020
CR-PLP-2020-
2551
08/10/2020
CR-PLP-2020-
2552
Entered AOP-38 "Acts of Nature" due to High Wind Warning
on August 10, 2020
08/11/2020
CR-PLP-2020-
2555
Start Up Transformer 1-2 Electrical Maintenance Failed to
Finish the Work as Scheduled due to Acts of Nature
08/11/2020
Procedures
4.11
Safety Function Determination Program
Corrective Action
Documents
CR-PLP-2020-
2009
Spalling of the Concrete Near Containment Vertical Tendon
V-140 Anchorage
06/24/2020
CR-PLP-2020-
2303
The Official Monthly Lake Michigan Elevation for June, as
Measured by the Calumet Harbor, Illinois Buoy, has
Exceeded the Assumed Starting Elevation for the Design
Basis Seiche Event
07/21/2020
CR-PLP-2020-
2316
Per CR-PLP-2020-02303 the Elevation of Lake Michigan in
the Area of the Plant has Exceeded the Assumed Design-
Basis Value for External Flooding Protection
07/22/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR-PLP-2020-
2365
Adjustment on HIC-0826, Instrument Air Regulator for CV-
26
07/27/2020
CR-PLP-2020-
2366
EK-EK-1171, Component CLG E-54B Hi-Lo Temp
07/28/2020
CR-PLP-2020-
2389
Operator Noted EVI-27/D2, BTRY D02 DC Volt
Indicator/Undervolt RLY Reading 129 8V
07/29/2020
CR-PLP-2020-
2394
Cooling Fan M201 in ED-09 was Discovered to be Operating
Approximately 18°F Warmer than the Other 2 Fans
07/30/2020
CR-PLP-2020-
2395
Discovered in ED-09, Wire 821 on TC No. 3, Terminal J4-11
was Approximately 33°F Warmer than the Similar Wires
07/30/2020
CR-PLP-2020-
2399
EK-1132, Service Water Pump Basket Strainer D/P Alarms
not Actuating at Proper D/P
07/30/2020
CR-PLP-2020-
2405
RT-202B Precals for Channels 1 and 2 were Calibrated
Above Stated Ranges
07/30/2020
CR-PLP-2020-
2941
Service Water Piping Inside Containment
09/02/2020
CR-PLP-2020-
2943
Service Water Piping Inside Containment
09/02/2020
Corrective Action
Documents
Resulting from
Inspection
CR-PLP-2020-
2432
Service Water P-7C was Removed from Service to Clean
BS-1320, P-7C Service Water Pump Basket Strainer
08/01/2020
CR-PLP-2020-
2617
Editorial Error at the Bottom of the Tabulation on FSAR
Page 5.8-33
08/18/2020
Engineering
Changes
86917
Continued Operation when Lake Michigan Design Basis
Levels are Exceeded
289
Concrete Spalling Near V-140 Tendon Anchorage on
Containment Dome
87503
Supplement to EC 87289 on ACI Bearing Strength
87696
Supplement to EC 87289 and EC 87503 on Steel Plate
Applied Stresses
Engineering
Evaluations
87503
Supplement to EC 87289 on ACI Bearing Strength
Miscellaneous
PLP-RPT-15-
00010
Palisades Nuclear Plant Flooding Hazard Re-Evaluation
Report
Procedures
QO-5,
Valve Stroke Testing Data Sheet CV-0821, CV-0822,
08/29/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
17
CV-0823, CV-0826
SOP-15
Palisades Nuclear Plant System Operating Procedure:
Service Water System
Work Orders
2922071
QO-5 -Vlv Test Proc (Inc Cont Isolation Vlvs)
05/26/2020
Corrective Action
Documents
CR-PLP-2020-
2423
Fan M-201 for ED-09 Inverter #4 was Replaced
07/31/2020
CR-PLP-2020-
2424
Buildup of Dirt & Dust on the Bottom of M1, M2 &M201 Heat
Sinks
07/31/2020
CR-PLP-2020-
2426
Service Water P-7B was Removed from Service to Clean
BS-1319, P-7B Service Water Pump Basket Strainer
07/31/2020
CR-PLP-2020-
2911
SSC: CV-3057, Safety Injection Refueling Water Tank
(SIRWT) Isolation
09/02/2020
Miscellaneous
Control Room Logs
07/28/2020
Failure Modes
and Effects
Worksheet
NI-3, Wide Range Nuclear Instrument
09/13/2020
Procedures
Troubleshooting Control of Maintenance Activities
09/23/2020
Offline Motor Electrical Testing
07/27/2020
PWR Core Loading Verification
09/16/2020
Off-Line Baker Testing of Motor EMA-1208 for P-52B
07/27/2020
RFL-V-9
Core Verification
RI-99
Left Channel Nuclear Instrumentation Calibrations
SOP-22
Work Orders
00550833
NI-1/3A, Indication Failed - Replace Suspect 8D's "A8 & A9"
09/21/2020
2864755
EEQ Maint-Comp. Cooling. EMA-1208, P-52B Motor
07/27/2020
2872985
Core Mapping System Setup and Operation
09/16/2020
Corrective Action
Documents
CR-PLP-2020-
2793
CV-0701, SG E-50A FW Regulating Valve
08/30/2020
CR-PLP-2020-
2795
Rod Deviation Alarms were Received
08/30/2020
CR-PLP-2020-
2796
RV-2006, Letdown Heat Exch E-58 Inlet Safety Relief and
Primary Coolant System (PCS)
08/30/2020
CR-PLP-2020-
2802
CV-2002 is not Opening with SV-2002B in AUTO
08/30/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR-PLP-2020-
2820
Boric Acid Leak was Identified on CRD-12
08/30/2020
CR-PLP-2020-
2821
Boric Acid Leak was Identified on CRD-18
08/30/2020
CR-PLP-2020-
2894
Air Hoses Were Ran Thru the Equipment Hatch Without Ops
Alignment and Hose Labeling per GOP-14
09/01/2020
CR-PLP-2020-
03094
T-2, Condensate Storage Tank
09/05/2020
CR-PLP-2020-
262
Control Room Operators Entered AOP-36, Loss of
Component Cooling
09/10/2020
CR-PLP-2020-
03620
Breaker 25H9 (Generator Output Breaker) Failed to Close
from the Control Room
09/18/2020
Corrective Action
Documents
Resulting from
Inspection
CR-PLP-2020-
2838
NRC Identified - During the Containment Walkdown a
Puddle of Oil was Found on the 590' Clean Waste Receiver
Tank Room About Half Under the 607' Catwalk
08/31/2020
Procedures
EM-04-08
Mode 3, Tave = 525°F Shutdown Margin Calculation
08/24/2020
PWR Reactivity Maneuver - Reactivity Plan Form
08/25/2020
GOP-14
Shutdown Cooling Operations
Corrective Action
Documents
CR-PLP-2020-
2471
PI-1475, Diesel Generator K-6A Fuel Oil Pressure was at 25
psig
08/05/2020
CR-PLP-2020-
2472
RO-128-1, Diesel Generator 1-1 24 Hour Load Run, Table
for Acceptance Criteria
08/05/2020
CR-PLP-2020-
2834
LLRT for Penetration MZ-42, Could not Establish <10sccm
on Step 5.2.13(h)2 and 3, Actual Reading was 30 sccm
08/31/2020
CR-PLP-2020-
2996
Leakage from Containment Penetration #15 was 8400 sccm
and Exceeded the 5000 sccm Troubleshooting Guideline
09/04/2020
CR-PLP-2020-
03806
CV-0847, SW Supply to Cont (MZ-12)
09/25/2020
Procedures
QO-1
Safety Injection System
QO-15
Inservice Test Procedure - Component Cooling Water
Pumps
QO-19B
Inservice Test Procedure - HPSI Pumps and Emergency
Safety System Check Valve Operability Test
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineered Safeguards System - Left Channel
09/14/2020
Work Orders
2871419
RT-8C - Engineered Safeguards System - Left Channel
09/14/2020
2928850
QO-15B, Inservice Test Procedure - Component Cooling
Pump P-52B
07/27/2020
Procedures
Access Control for Radiologically Controlled Areas
EN-RP-106-01
Radiological Survey Guidlines
Alpha Monitoring
Air Sampling
Radiation Work
Permits (RWPs)
200424
Scaffolding Activities in Containment
200433
Refuel Project: Disassembly of the Reactor Head and
Associated Work Activities
200454
Steam Generator Primary Side Activities
ALARA Plans
200424
Scaffolding Activities in Containment
200433
Refuel Project: Disassembly of the Reactor Head and
Associated Work Activities
200454
Steam Generator Primary Side Activities
Procedures
ALARA Program
71151
Miscellaneous
NRC Performance Indicators 2Q2020
04/01/2020 -
06/30/2020
NRC Performance Indicators 1Q2020
01/01/2020 -
03/31/2020
NRC Performance Indicators 4Q2019
10/01/2019 -
2/31/2019
NRC Performance Indicators 3Q2019
07/01/2019 -
09/330/2019
NRC Performance Indicators 2Q2019
04/01/2019 -
06/30/2019
NRC Performance Indicators 4Q2018
10/01/2018 -
2/31/2018
NRC Performance Indicators 3Q2018
07/01/2018 -
09/30/2018
Procedures
NRC Performance Indicators 1Q2019
01/01/2019 -
03/31/2019
Corrective Action
CR-PLP-2020-
CV-0826 CCW HX E-54B SW Outlet Pinned Incorrectly
07/27/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
2365
Procedures
QO-5
Valve Test Procedure (Includes Containment Isolation
Valves)
109
SOP-15
Service Water System
70