IR 05000255/2020003

Integrated Inspection Report 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: DPR-20 Report Number: 05000255/2020003 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 Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Palisades Nuclear Plant, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

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.

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,

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 Type Designation Description or Title Revision or

Procedure Date

71111.04 Corrective Action CR-PLP-2020- Protected Equipment for 1-2 Emergency Diesel Generator 07/06/2020

Documents 02120

CR-PLP-2020- Notification per MISO that Maintenance Activities Must be 07/06/2020

2126 Curtailed Due to Generation Availability Constraints

CR-PLP-2020- During Performance of MO-7A-1, FI-0890, Diesel Generator 07/08/2020

2149 1-1 Service Water Flow was Reading 710gpm

CR-PLP-2020- VC-10 Suction Pressure Cycling From 52 psig to 58 psig on 07/21/2020

298 PI-1676

CR-PLP-2020- P-7B Service Water Pump Basket Strainer 07/25/2020

2345

CR-PLP-2020- Corrosion Found During Rounds in Station Battery Number 2 07/26/2020

2354

CR-PLP-2020- Induction Disc of the GE 12IAC53A101A Relay 151-106 X- 08/10/2020

2542 Phase was Stuck to the Backstop of the Time Dial/Lever

Corrective Action CR-PLP-2020- NRC Identified the Floor Drain Cover on the South End of 07/06/2020

Documents 02129 the 1-2 Emergency Diesel Generator Ajar

Resulting from CR-PLP-2020- The NRC Identified that the 1-2 Emergency Diesel 07/06/2020

Inspection 02130 Generator Vents are Dirty and may Require Cleaning

CR-PLP-2020- NRC Identified a Potential Oil Leak on the North End of the 07/06/2020

2131 1-1 Emergency Diesel Generator

CR-PLP-2020- NRC Identified There is Vegetation Growing on the North 07/23/2020

2329 and North East Sides of EX-17, Station Transformer 17

CR-PLP-2020- NRC Identified Debris on the Floor of the 1-1 and 1-2 EDG 07/23/2020

2330 Rooms

Drawings M-221 Piping & Instrumentation Diagram, Spent Fuel Pool Cooling 61

System, Sheet 2

Miscellaneous DBD 2.07 Design Basis Document for Spent Fuel Pool Cooling System 5

Procedures AOP-26 Loss of Spent Fuel Pool Cooling 3

SOP-27 Fuel Pool System 72

71111.05 Corrective Action CR-PLP-2020- PI-5350A, Fire Protection System Header Pressure was 07/30/2020

Documents 02416 Trending Down

Fire Plans Pre-Fire Plan 13B Charging Pump Rooms / Elevation 590' 5

Inspection Type Designation Description or Title Revision or

Procedure Date

Pre-Fire Plan 2 Cable Spreading Room; Elevation 607' 5

Pre-Fire Plan 26 Southwest Cable Penetration Room; Elevation 590' & 607' 5

Pre-Fire Plan 4 1-C Switchgear Room and Manhole 1, 2, & 3/Elevation 590' 5

71111.06 Corrective Action CR-PLP-2020- Expansion Joint XJ-0421 Flood Barrier on HB-23-3" was 08/04/2020

Documents 02461 Identified as Having a Slit in the Joint Approximately Midway

Down the Southern Side of the Joint

Miscellaneous DBD 7.08 Design Basis Document Plant Protection Against Flooding 6

Procedures AOP-39 Internal Plant Flooding 1

71111.08P Corrective Action CR-PLP-2020- Ultrasonic Data Analysis of a Relevant Indication on 09/11/2020

Documents 03380 Penetration 34 on the Reactor Vessel Head

Resulting from CR-PLP-2020- Ultrasonic Data Analysis of a Relevant Indication on 09/13/2020

Inspection 03427 Penetration 17 on the Reactor Vessel Head

Procedures 54-ISI-400-023 NONDESTRUCTIVE EXAMINATION PROCEDURE 12/12/2018

Multi-Frequency Eddy Current Examination of SG Tubing

54-ISI-619-000 Automated Ultrasonic Examination of Open Tube RPV 07/30/2020

Closure Head Penetrations-Palisades Specific

CEP-NDE-0955 Visual Examination (VE) of Bare-Metal Surfaces 307

LMT-10-PAUT- Fully Encoded Phased Array Ultrasonic Examination of 3

007 Dissimilar Metal Piping Welds

SEP-BAC-PLP- Boric Acid Corrosion Control Program Engineering Nuclear 4

001 Programs Applicable Sites

71111.11Q Miscellaneous SES-405 LOR Simulator Exam Scenario 1

Procedures GOP-14 Reduced Inventory Checklist 53

GOP-8 Power Reduction and Plant Shutdown to Mode 2 or Mode 3 40

= 525°F

71111.12 Corrective Action CR-PLP-2018- CV-0869, CAC VHX-4 SW Inlet, Valve Actuator Moved in the 11/09/2018

Documents 05815 Closed or Open Direction, but Valve Itself did not Move

CR-PLP-2019- Baker Offline Motor Test Could not be Completed 12/16/2019

04925

CR-PLP-2020- Discharge Accumulator for P-55C Charging Pump the "As 08/05/2020

2475 Found" Pressure of the Tank Bladder was 1287 psig

CR-PLP-2020- Charging Pump "As Found" Pressure of the Tank Bladder 08/05/2020

2476 was 0.0 psig

CR-PLP-2020- Critical Service Water System (CSW) has Exceeded the 08/10/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

2543 Near (a)(1) Threshold

CR-PLP-2020- Exceeded Maintenance Rule (MR) Performance Criteria 09/07/2020

03184 (PC) for Number of Functional Failures (#) in 24 Months for

the Main Steam System

Miscellaneous System Health Chemical & Volume Control System 2018

Report

System Health Chemical & Volume Control System 2019

Report

System Health CSW - Critical Service Water Q2-2019

Report

System Health CSW - Critical Service Water Q2-2020

Report

System Health CSW - Critical Service Water Q4-2018

Report

System Health CSW - Critical Service Water Q4-2019

Report

71111.13 Corrective Action CR-PLP-2020- Removed from Service to Clean BS-1318, P-7A Service 07/31/2020

Documents 02421 Water Pump Basket Strainer

CR-PLP-2020- Control Room Envelope 08/10/2020

2551

CR-PLP-2020- Entered AOP-38 "Acts of Nature" due to High Wind Warning 08/11/2020

2552 on August 10, 2020

CR-PLP-2020- Start Up Transformer 1-2 Electrical Maintenance Failed to 08/11/2020

2555 Finish the Work as Scheduled due to Acts of Nature

Procedures 4.11 Safety Function Determination Program 7

71111.15 Corrective Action CR-PLP-2020- Spalling of the Concrete Near Containment Vertical Tendon 06/24/2020

Documents 02009 V-140 Anchorage

CR-PLP-2020- The Official Monthly Lake Michigan Elevation for June, as 07/21/2020

2303 Measured by the Calumet Harbor, Illinois Buoy, has

Exceeded the Assumed Starting Elevation for the Design

Basis Seiche Event

CR-PLP-2020- Per CR-PLP-2020-02303 the Elevation of Lake Michigan in 07/22/2020

2316 the Area of the Plant has Exceeded the Assumed Design-

Basis Value for External Flooding Protection

Inspection Type Designation Description or Title Revision or

Procedure Date

CR-PLP-2020- Adjustment on HIC-0826, Instrument Air Regulator for CV- 07/27/2020

2365 0826

CR-PLP-2020- EK-EK-1171, Component CLG E-54B Hi-Lo Temp 07/28/2020

2366

CR-PLP-2020- Operator Noted EVI-27/D2, BTRY D02 DC Volt 07/29/2020

2389 Indicator/Undervolt RLY Reading 129 8V

CR-PLP-2020- Cooling Fan M201 in ED-09 was Discovered to be Operating 07/30/2020

2394 Approximately 18°F Warmer than the Other 2 Fans

CR-PLP-2020- Discovered in ED-09, Wire 821 on TC No. 3, Terminal J4-11 07/30/2020

2395 was Approximately 33°F Warmer than the Similar Wires

CR-PLP-2020- EK-1132, Service Water Pump Basket Strainer D/P Alarms 07/30/2020

2399 not Actuating at Proper D/P

CR-PLP-2020- RT-202B Precals for Channels 1 and 2 were Calibrated 07/30/2020

2405 Above Stated Ranges

CR-PLP-2020- Service Water Piping Inside Containment 09/02/2020

2941

CR-PLP-2020- Service Water Piping Inside Containment 09/02/2020

2943

Corrective Action CR-PLP-2020- Service Water P-7C was Removed from Service to Clean 08/01/2020

Documents 02432 BS-1320, P-7C Service Water Pump Basket Strainer

Resulting from CR-PLP-2020- Editorial Error at the Bottom of the Tabulation on FSAR 08/18/2020

Inspection 02617 Page 5.8-33

Engineering 86917 Continued Operation when Lake Michigan Design Basis 0

Changes Levels are Exceeded

289 Concrete Spalling Near V-140 Tendon Anchorage on 0

Containment Dome

87503 Supplement to EC 87289 on ACI Bearing Strength 0

87696 Supplement to EC 87289 and EC 87503 on Steel Plate 0

Applied Stresses

Engineering 87503 Supplement to EC 87289 on ACI Bearing Strength 0

Evaluations

Miscellaneous PLP-RPT-15- Palisades Nuclear Plant Flooding Hazard Re-Evaluation 1

00010 Report

Procedures QO-5, Valve Stroke Testing Data Sheet CV-0821, CV-0822, 08/29/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

17 CV-0823, CV-0826

SOP-15 Palisades Nuclear Plant System Operating Procedure: 69

Service Water System

Work Orders 52922071 QO-5 -Vlv Test Proc (Inc Cont Isolation Vlvs) 05/26/2020

71111.19 Corrective Action CR-PLP-2020- Fan M-201 for ED-09 Inverter #4 was Replaced 07/31/2020

Documents 02423

CR-PLP-2020- Buildup of Dirt & Dust on the Bottom of M1, M2 &M201 Heat 07/31/2020

2424 Sinks

CR-PLP-2020- Service Water P-7B was Removed from Service to Clean 07/31/2020

2426 BS-1319, P-7B Service Water Pump Basket Strainer

CR-PLP-2020- SSC: CV-3057, Safety Injection Refueling Water Tank 09/02/2020

2911 (SIRWT) Isolation

Miscellaneous Control Room Logs 07/28/2020

Failure Modes NI-3, Wide Range Nuclear Instrument 09/13/2020

and Effects

Worksheet

Procedures EN-MA-125 Troubleshooting Control of Maintenance Activities 09/23/2020

EN-MA-134 Offline Motor Electrical Testing 07/27/2020

EN-RE-326 PWR Core Loading Verification 09/16/2020

EN-WM-105 Off-Line Baker Testing of Motor EMA-1208 for P-52B 07/27/2020

RFL-V-9 Core Verification 9

RI-99 Left Channel Nuclear Instrumentation Calibrations 18

SOP-22 Emergency Diesel Generator 80

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

71111.20 Corrective Action CR-PLP-2020- CV-0701, SG E-50A FW Regulating Valve 08/30/2020

Documents 02793

CR-PLP-2020- Rod Deviation Alarms were Received 08/30/2020

2795

CR-PLP-2020- RV-2006, Letdown Heat Exch E-58 Inlet Safety Relief and 08/30/2020

2796 Primary Coolant System (PCS)

CR-PLP-2020- CV-2002 is not Opening with SV-2002B in AUTO 08/30/2020

2802

Inspection Type Designation Description or Title Revision or

Procedure Date

CR-PLP-2020- Boric Acid Leak was Identified on CRD-12 08/30/2020

2820

CR-PLP-2020- Boric Acid Leak was Identified on CRD-18 08/30/2020

2821

CR-PLP-2020- Air Hoses Were Ran Thru the Equipment Hatch Without Ops 09/01/2020

2894 Alignment and Hose Labeling per GOP-14

CR-PLP-2020- T-2, Condensate Storage Tank 09/05/2020

03094

CR-PLP-2020- Control Room Operators Entered AOP-36, Loss of 09/10/2020

262 Component Cooling

CR-PLP-2020- Breaker 25H9 (Generator Output Breaker) Failed to Close 09/18/2020

03620 from the Control Room

Corrective Action CR-PLP-2020- NRC Identified - During the Containment Walkdown a 08/31/2020

Documents 02838 Puddle of Oil was Found on the 590' Clean Waste Receiver

Resulting from Tank Room About Half Under the 607' Catwalk

Inspection

Procedures EM-04-08 Mode 3, Tave = 525°F Shutdown Margin Calculation 08/24/2020

EN-RE-302 PWR Reactivity Maneuver - Reactivity Plan Form 08/25/2020

GOP-14 Shutdown Cooling Operations 53

71111.22 Corrective Action CR-PLP-2020- PI-1475, Diesel Generator K-6A Fuel Oil Pressure was at 25 08/05/2020

Documents 02471 psig

CR-PLP-2020- RO-128-1, Diesel Generator 1-1 24 Hour Load Run, Table 08/05/2020

2472 for Acceptance Criteria

CR-PLP-2020- LLRT for Penetration MZ-42, Could not Establish <10sccm 08/31/2020

2834 on Step 5.2.13(h)2 and 3, Actual Reading was 30 sccm

CR-PLP-2020- Leakage from Containment Penetration #15 was 8400 sccm 09/04/2020

2996 and Exceeded the 5000 sccm Troubleshooting Guideline

CR-PLP-2020- CV-0847, SW Supply to Cont (MZ-12) 09/25/2020

03806

Procedures QO-1 Safety Injection System 70

QO-15 Inservice Test Procedure - Component Cooling Water 40

Pumps

QO-19B Inservice Test Procedure - HPSI Pumps and Emergency 44

Safety System Check Valve Operability Test

Inspection Type Designation Description or Title Revision or

Procedure Date

RT-8C Engineered Safeguards System - Left Channel 09/14/2020

Work Orders 52871419 RT-8C - Engineered Safeguards System - Left Channel 09/14/2020

2928850 QO-15B, Inservice Test Procedure - Component Cooling 07/27/2020

Pump P-52B

71124.01 Procedures EN-RP-101 Access Control for Radiologically Controlled Areas 15

EN-RP-106-01 Radiological Survey Guidlines 6

EN-RP-122 Alpha Monitoring 10

EN-RP-131 Air Sampling 17

Radiation Work 20200424 Scaffolding Activities in Containment 00

Permits (RWPs) 20200433 Refuel Project: Disassembly of the Reactor Head and 00

Associated Work Activities

200454 Steam Generator Primary Side Activities 00

71124.02 ALARA Plans 20200424 Scaffolding Activities in Containment 00

200433 Refuel Project: Disassembly of the Reactor Head and 00

Associated Work Activities

200454 Steam Generator Primary Side Activities 00

Procedures EN-RP-110 ALARA Program 14

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

71152 Corrective Action CR-PLP-2020- CV-0826 CCW HX E-54B SW Outlet Pinned Incorrectly 07/27/2020

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents 02365

Procedures QO-5 Valve Test Procedure (Includes Containment Isolation 109

Valves)

SOP-15 Service Water System 70

16