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

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.

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

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.04

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

AOP-26

Loss of Spent Fuel Pool Cooling

SOP-27

Fuel Pool System

71111.05

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'

71111.06

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

AOP-39

Internal Plant Flooding

71111.08P

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

71111.12

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

71111.13

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

Control Room Envelope

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

71111.15

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

71111.19

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

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

RI-99

Left Channel Nuclear Instrumentation Calibrations

SOP-22

Emergency Diesel Generator

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

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

EN-RE-302

PWR Reactivity Maneuver - Reactivity Plan Form

08/25/2020

GOP-14

Shutdown Cooling Operations

71111.22

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

RT-8C

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

71124.01

Procedures

EN-RP-101

Access Control for Radiologically Controlled Areas

EN-RP-106-01

Radiological Survey Guidlines

EN-RP-122

Alpha Monitoring

EN-RP-131

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

71124.02

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

EN-RP-110

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

71152

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