IR 05000454/2021002

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Integrated Inspection Report 05000454/2021002; 05000455/2021002; and 07200068/2021001
ML21215A078
Person / Time
Site: Byron  Constellation icon.png
Issue date: 08/04/2021
From: Hironori Peterson
Region 3 Branch 3
To: Rhoades D
Exelon Generation Co
References
IR 2021001
Download: ML21215A078 (18)


Text

SUBJECT:

BYRON STATION - INTEGRATED INSPECTION REPORT 05000454/2021002; 05000455/2021002; AND 07200068/2021001

Dear Mr. Rhoades:

On June 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Byron Station. On July 12, 2021, the NRC inspectors discussed the results of this inspection with Mr. J. Kowalski, Site Vice President, 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, Hironori Peterson, Chief Branch 3 Division of Reactor Projects Docket Nos. 05000454; 05000455; 07200068 License Nos. NPF-37 and NPF-66

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000454; 05000455; 007200068

License Numbers:

NPF-37 and NPF-66

Report Numbers:

05000454/2021002; 05000455/2021002; 07200068/2021001

Enterprise Identifier:

I-2021-002-0068; 1-2021-001-0160

Licensee:

Exelon Generation Company, LLC

Facility:

Byron Station

Location:

Byron, IL

Inspection Dates:

April 01, 2021 to June 30, 2021

Inspectors:

D. Betancourt-Roldan, Senior Resident Inspector

J. Dalzell, Project Engineer

C. Thompson, Illinois Emergency Management Agency

J. Weigandt, Resident Inspector

Approved By:

Hironori Peterson, Chief

Branch 3

Division of Reactor Projects

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Byron Station, 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

Unit 1 began the inspection period operating at full power. With the exception of minor reductions in power to support scheduled testing activities or small load changes requested by the transmission dispatcher, the unit remained at or near full power for the entire inspection period.

Unit 2 began the inspection period operating at full power. With the exception of minor reductions in power to support scheduled testing activities or small load changes requested by the transmission dispatcher, the unit remained at or near full power for the entire 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 and regional 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, increasing the amount of time on site as local COVID-19 conditions permitted.

As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities; and completed on site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.

REACTOR SAFETY

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated summer readiness of offsite and alternate alternating current (AC) power systems April 19 through June 1, 2021.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Unit 1 'A' Auxiliary Feedwater (AF) during 'B' battery issue on April 24, 2021 (2)2A Emergency Diesel Generator (EDG) during Station Auxiliary Transformer (SAT)window on May 5, 2021
(3) Fire Protection System Train A while the 'B' Fire Pump was out of service on May 15, 2021
(4) Unit 1 Instrument Power and 125 Volt Direct Current (DC) during 1B Diesel Generator (DG) outage on June 16, 2021
(5) Diesel fuel oil during 2B EDG monthly test and after fuel oil transfer tests on June 27, 2021

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 AF begun during the first quarter 2021 inspection period and completed on May 14, 2021.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) Fire Zone (FZ) 8.31 Northeast: Turbine Building 401' Elevation on April 7, 2021
(2) FZs 3.2A/B/C/D/E-1 PFPs: Unit 1 Lower Cable Spreading Rooms on April 30, 2021
(3) FZs 3.2A/B/C/D/E-2 PFPs: Unit 2 Lower Cable Spreading Rooms on April 30, 2021
(4) FZ 11.2-0 North/11.3-0 South: Auxiliary Building General Area 364' Elevation on May 3, 2021
(5) FZs 18.12-0 & 18.13-0: Circulating Water Pumphouse on May 15, 2021

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) Turbine Building basement on April 16, 2021

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 Sample)

The inspectors observed and evaluated the following licensed operator activities in the control room:

(1) Various activities involving on-watch operations crews. These activities included, but were not limited to:

Unit 1 downpower 100MWe for Advanced Nuclear Dispatch on April 9, 2021

Dilution on Unit 1 on June 1, 2021

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) Maintenance effectiveness and performance review of the pressurizer heaters on April 21, 2021
(2) Maintenance effectiveness and performance review of the Technical Support Center (TSC) ventilation on June 14, 2021

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) Unit 2 'B' Component Cooling Pump as set forth in Work Order (WO) 5006411 on April 17, 2021
(2) Evaluation of the scheduled Risk Informed Completion Time (RICT) window SAT outage on May 3, 2021 (3)2A EDG work window as set forth in WO 5063615 and Engineering Change (EC)

===632199 on June 2, 2021

(4) 1B EDG work window on June 14, 2021

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01)===

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) NRC Information Notice 2017-06 evaluation as documented in Action Request (AR) 04415085 on April 9, 2021
(2) Evaluation of the operability of a lube oil leak on the 1A AF pump as documented in AR 04417861 on April 20, 2021
(3) Evaluation of the operability of 1HK-AF031A flow control POT needs adjustment as documented in AR 4418342 on April 22, 2021
(4) Evaluation of the operability of the 1A EDG manually secured due to exhaust leak as documented in AR 04419745 on April 28, 2021
(5) Evaluation of the operability of 1SX68AB-1.5 pinhole leak (OP 2021-001) on May 3, 2021

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (3 Samples)

The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:

(1)2BOSR 8.6.1-2, 2BHSSR 8.4.2-2, and MA-BY-223.053: DC 211 Charger and Battery return to service after inspection as set forth in WOs 5136320, 4966367, and

===4945435 respectively, on April 10, 2021

(2) Unit 2 'B' CC Pump as set forth in WOs 5006411 and 5110415 on April 17, 2021 (3)1BOSR 5.5.8.SI.5-2A 1B Safety Injection (SI) Inservice Test (IST) Group A Pump Test as set forth in WO 5126604 on May 13, 2021

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1)2B DG Semiannual Run as set forth in WO 05086672 on April 20, 2021

(2) Unit 2 Engineered Safety Feature (ESF) K602 Relay Test as set forth in WO 4918193 on April 24, 2021 (3)1A DG Testing on April 30, 2021 Inservice Testing (IP Section 03.01)===

(1)2BOSR 5.5.8.SI.5-2a, Group A IST Requirements for SI Pump 2SI01PB as set forth in WO 5118448 on April 17,

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===

(1) Unit 1 (April 1, 2020 - March 31, 2021)
(2) Unit 2 (April 1, 2020 - March 31, 2021)

MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)

(1) Unit 1 (April 1, 2020 - March 31, 2021)
(2) Unit 2 (April 1, 2020 - March 31, 2021)

MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)

(1) Unit 1 (April 1, 2020 - March 31, 2021)
(2) Unit 2 (April 1, 2020 - March 31, 2021)

71152 - Problem Identification and Resolution

Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)

The inspectors reviewed the licensees implementation of its Corrective Action Program (CAP) related to the following issues:

(1) Unit 1 AF Discharge Valve Hand Controller Settings as noted in CAPs 4418342,

4418342, and 4430576 71153 - Follow-up of Events and Notices of Enforcement Discretion Reporting (IP Section 03.05)

(1) Evaluated reportability of loss of TSC Heating, Ventilation and Air Conditioning compressors as documented in ARs 4421161 & 4427773 for the week ending June 19, 2021
(2) Evaluated the reportability of Unit 1 Containment Ventilation Isolation as documented in AR 4430194 on June 18, 2021
(3) Evaluated reportability of loss of Unit 2 annunciators as documented in AR 4429603 on June 16,

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 60855 - Operation of an Independent Spent Fuel Storage Installation The inspectors evaluated the licensees independent spent fuel storage installation (ISFSI) cask loading activities on March 29 through April 2, 2021. Specifically, the inspectors observed the following activities:

Heavy lifts of the loaded transfer cask from the wet pit to the cask processing area

Lid-to-shell root pass welding

Canister processing including forced helium dehydration

Closure ring welding and non-destructive weld evaluations

Stack-up and download of the Multi-Purpose Canister (MPC) from the HI-TRAC into the storage cask (HI-STORM) and

Radiological field surveys The inspectors performed walkdowns of the ISFSI pad, including independent radiation surveys, and walkdowns of the ISFSI haul path and vertical cask transporter.

The inspectors evaluated the following:

Spent fuel selection for the cask for this loading campaign

Selected CAPs action requests

Selected 72.48 screenings and evaluations

INSPECTION RESULTS

Observation: Unit 1 Auxiliary Feedwater Discharge Valve Hand Controller Settings 71152 On April 19, 2021, while performing a control room panel walkdown the inspectors noted that the AF discharge flow control valve hand controller (HK) meter indications and the potentiometer settings did not match each other. The inspectors noted that the HKs meters indicated 70 percent +/- 2 percent while the potentiometer settings appeared to vary between 6.8 and 7.1. Upon identification, the inspectors questioned the operators on shift of the condition. The operators then entered the condition into the Corrective Action Program as CAPs 4418342 and 4418343 for 1HK-AF0031A and 38A, 1A & 1D AF to Steam Generator Setpoint Stations being set above 6.8.

To further evaluate the condition the inspectors proceeded to review the related reference documents and noted that the HKs setpoint should be 6.8 for 1AF005A/B/C/D/E/F/G/H, AF Discharge Flow Control Air Operated Valves to yield 170 gpm. Additionally, 1BOL 7.g, AF Flow Control Valves, included direction in part to apply Technical Requirement Manual (TRM) 3.7.g condition C, which states in part that:

Condition C: One or more AF Flow Control Valve(s) not capable of throttling flow as assumed in the safety analysis for Steam Generator Tube Rupture Margin to Overfill event.

(Note 2) C.1 Restore AF Flow Control Valve(s) to OPERABLE status. 30 days.

Note 2: Condition C is applicable for any AF flow control valve thats flow control pot (1HK-AF031-38A) is adjusted to a setpoint above that specified within 1BGP 100-1A or is incapable of being throttled to control flow at or below the value specified within Design Analysis for Steam Generator Tube Rupture Margin to Overfill, CN-CRA-07-47 Revision 4.

(Pot Setpoint of 6.8 - 170 gpm).

The inspectors reviewed the observations related response in the CAP products. According to the CAP notes, output voltage checks were performed and verified that the current setting would result in the desired voltage and flow. Additionally, it was reported that the meters may vary due to not being calibrated at a specific frequency. From their review the inspectors questioned why the TRM condition was not entered upon discovery as the condition appeared to be met. The inspectors identified that this failure to follow the 1BOL 7.g requirements was a performance deficiency. The deficiency was determined to be of minor significance since the output voltage was verified to result in the desired flow of 170 gpm.

Corrective actions planned by the licensee included revising operating procedures to provide guidance on when to enter the TRM action.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

On July 12, 2021, the inspectors presented the integrated inspection results to Mr. J. Kowalski, Site Vice President, and other members of the licensee staff.

On April 7, 2021, the inspectors presented the Independent Spent Fuel Storage Installation inspection results to Mr. H. Welt, Plant Manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Calculations

HI-2146074

Thermal Evaluation of the Hi-TRAC in the Decon Pit at

Byron/Braidwood

Corrective Action

Documents

Corrective Action Reports from March 2018 through

April 2021

03/01/2018 -

04/30/2021

Corrective Action

Documents

Resulting from

Inspection

AR 04413082

NRC ID - Improper Work Order Closure

03/31/2021

2.48 Screening

No. 72.48-102

Corrected 72.48 for Dry Cask License Upgrade 72.48-102

2.48 Screening

No. 72.48-168

HI-TRAC Movement Within the Fuel Building

2.48 Screening

No. 72.48-170

DCR to Incorporate Revision to Analysis No. BYR13-063 for

Replacement Nylatron

2.48 Screening

No. 72.48-174

EC 621659/BFP FH-69/BFP FH-70/BFP FH-82/BFP

FH-83/OU-MW-671-300/OU-MW-671-F-01/BYNPS 72.212

Evaluation Report Change Request 06-06

2.48 Screening

No. 72.48-177

Holtec Supplier Manufacturing Deviation Report (SMDR)

No. 1024-2687 Review

2.48 Screening

No. 72.48-179

Replace 3" HI-STORM Lift Bracket Strongback Spacers (for

Ancillary #107)

2.48 Screening

No. 72.48-182

ISFSI Pad/CTOZ Joint Surface Alternate Detail Repair

Method

2.48 Screening

No. 72.48-191

HI-TRAC Movement Within the Fuel Building

2.48 Screening

No. 72.48-192

Analysis No. HI-2146074, Revision 4 - Site-Specific Thermal

Analysis

2.48 Screening

No. 72.48-197

Holtec Supplier Manufacturing Deviation Report (SMDR)

Affecting HI-STORM Serial No. 1118

2.48 Screening

No. 72.48-200

HI-TRAC Loading Operations

60855

Engineering

Changes

2.48 Screening

Approve Use of Nylon-Insert Locknut on HI-TRAC Lift Yoke

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

No. 72.48-202

Spacer Pins

2.48 Screening

No. 72.48-207

Gouge on MPC Lid of MPC Serial No.32-502

2.48 Screening

No. 72.48-209

Spent Fuel Cask Site Transportation

2.48 Screening

No. 72.48-217

Supplier Manufacturing Deviation Report No. 1024-1831

Revision 1

EC0000628809

Replace Existing FH Building Overhead Crane SD-41 Weigh

System Controller with a Model SD-50 Controller

LMS Qual Matrix Report

01/05/2021

Physical Inventory of Byron ISFSI MPC-32-0644

03/29/2021

2.212 Change

Request No.

07-02

2.212 Evaluation Change Request

03/04/2019

2.212 Change

Request No.

08-01

2.212 Evaluation Change Request

06/14/2020

2.212 Change

Request No.

08-02

2.212 Evaluation Change Request

06/12/2020

BYR11-182

Byron Cask Loader Database Cask Model and Limits Update

for 2012 ISFSI Campaign

BYR19-006

Byron Cask Model Update for 2019 ISFSI Campaign - ISFSI

BYR20-018

Fuel Selection Package and Alternate List for the Byron 2021

ISFSI Campaign

CC-AA-501-1020

Contractor Welding Review

01/28/2021

NCR 0832-51

Non-Conformance Report for Pool Lid

Miscellaneous

RRTI-2730-002

Response to Request for Technical Information for Gouge in

MPC-32 S/N 502

Report No.

914667-644-01

through 914667-

644-04

Report of Non-Destructive Examination Lid-to-Shell Weld

03/30/2021

NDE Reports

Report No.

Report of Non-Destructive Examination Closure Welding

03/31/2021

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

914667-644-05

through

914667-644-07

WO # 04963593-

Helium Leak Test Report

03/31/2021

2018 Annual Radiological Environmental Operating Report

04/18/2019

2018 Annual Radioactive Effluent Release Report

04/18/2019

RP-AA-307

Braidwood and Byron ISFSI Radiation Survey

04/01/2021

Radiation

Surveys

Survey Map # 292

ISFSI Pad Radiation Surveys 2018-2021

03/05/2021

Radiation Work

Permits (RWPs)

RP-AA-401

Dry Cask Storage ALARA Plan

01/25/2021

NOSA-BYR-20-10

Independent Spent Fuel Storage Installation Audit Report

10/07/2020

Self-Assessments

PI-AA-126-1001-

F-01

BYRON Spent Fuel Loading Campaign (SFLC)

Readiness Assessment

01/22/2021

PMID/RQ

00191464-01

ISFSI Pad Structural Inspection (5 Years)

10/13/2020

WO04874413-01

LR-FHB-Overhead Bridge Crane Mech Inspection

01/06/2020

WO04884074-01

EWP EM Crane Inspection (Fuel Handling Bldg) - 0HC03G

01/06/2020

WO04963593

RXS Perform Special Lifting Device INSP/TEST per BHP

FH-85

2/09/2020

Work Orders

WO04982062-01

EWP MM:0FH05G INSP Spent Fuel Pit/HNDLNG Machine

(LR)

11/23/2020

EN-AA-402-0005

Extreme Heat Implementation

71111.01

Procedures

EN-BY-402-0005

Extreme Heat Implementation

4418342

1HK-AF036A AF Flow Control POT Needs Adjustment

04/22/2021

Corrective Action

Documents

Resulting from

Inspection

4418343

1HK-AF031A AF Flow Control POT Needs Adjustment

04/22/2021

Drawings

M-52 sh. 5

Diagram of Fire Protection at Circulating Water Pumphouse

AL

1BGP 100-1A1

Controller Setpoints 1PM06J

BOP AF-E1A

Auxiliary Feedwater Train "A" Electrical Lineup

BOP AF-M1A

Auxiliary Feedwater Train "A" Valve Lineup

BOP DC-E1

DC Battery & Distribution Center Electrical Lineup

71111.04

Procedures

BOP FP-M1

Fire Protection System Valve Lineup

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

BOP IP-1

Instrument Bus Inverter Startup

BOP IP-1E

Instrument Power Electrical Lineup

20437

NRC Identified: LCSR Housekeeping

04/30/2021

20499

NRC Identified: 0DSD401 Door Closer Not Attached

04/30/2021

20500

NRC Identified: LCSR Housekeeping Items

04/30/2021

23478

NRC Identified: Condition Noted in U1 LCSR Area

05/13/2021

Corrective Action

Documents

Resulting from

Inspection

27381

NRC Identified: Gasket on 0DSD408 Degraded

06/03/2021

PFB TB FZ 8.3-1

Turbine Building 401'-0" ELEV, Unit 1 Turbine Building NE

PFP FZ 11.3-0

North

Auxiliary Building 364' 0" Elev General Area - North

PFP FZ 11.3-0

South

Auxiliary Building 364' 0" Elev General Area South

PFP FZ 18.12-0

AND FZ 18.13-0

Circulating Water Pump House / 0B Fire Pump Room

PFP FZ 3.2-0

U2 Auxiliary BLDG 439'-0" Elevation, Cable Spreading Room

PFP FZ 3.2A-1

U1 Auxiliary Building 439'-0" Elevation, Lower Cable

Spreading Room

PFP FZ 3.2B-1

U1 Auxiliary Building 439'-0" Elevation, Lower Cable

Spreading Room

PFP FZ 3.2B-2

U2 Auxiliary Building 439'-0" Elevation, Lower Cable

Spreading Room

PFP FZ 3.2C-1

U1 Auxiliary Building 439'-0" Elevation, Lower Cable

Spreading Room

PFP FZ 3.2C-2

U2 Auxiliary Building 439'-0" Elevation, Lower Cable

Spreading Room

PFP FZ 3.2D-1

U1 Auxiliary Building 439'-0" Elevation, Lower Cable

Spreading Room

PFP FZ 3.2D-2

U2 Auxiliary Building 439'-0" Elevation, Lower Cable

Spreading Room

PFP FZ 3.2E-1

Auxiliary BLDG 439'-0" Elev. Unit 1 Division 11 Cable Riser,

LCSR

PFP FZ 3.2E-2

Auxiliary BLDG 439'-0" Elev. Unit 2 Cable Riser

71111.05

Fire Plans

PFP FZ3.2A-2

U2 Auxiliary Building 439'-0" Elevation, Lower Cable

Spreading Room

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.06

Engineering

Evaluations

BB-AA-PRA-012

Braidwood/Byron Flood Scenarios

04308126

TSC Compressor 1 Tripped High Refrigerant Pressure

01/05/2020

04327769

IST Stroke Time Failure

04/17/2020

04327798

Pzr Heater Ground Alarm Group A Backup Heater

03/19/2020

04347948

TSC Condensing Unit Trouble

06/04/2020

71111.12

Corrective Action

Documents

04366934

U-1 Pressurizer Pressure Control Not Responding Normally

09/02/2020

4416548

NRC Identified: Discovered an Employees Badge was Worn

Off

04/14/2021

Corrective Action

Documents

Resulting from

Inspection

23122

PM 4KV Cubicle Inspection and Tagout Procedure

Enhancement

05/12/2021

Miscellaneous

RICT Package

2BOA ELEC-5

Local Emergency Control of Safe Shutdown Equipment

Unit 2

108

OP-AA-108-117

Protected Equipment Program

Procedures

OP-BY-108-117-

1000

Byron Protected Equipment Program

71111.13

Work Orders

5006411

(Sample/Change) Component Cooling Pump 2B

04/15/2021

04417861

Review UT Inspection of 1A01PA Pump Lube Oil Piping

04/20/2021

4415085

NRC DBAI: NRC information Notice 2017-06 Evaluation

04/08/2021

Corrective Action

Documents

4419745

1A DG Manually Secured Due to Exhaust Leak

04/28/2021

04418342

1HK-AF036A, AF Flow Control POT Needs Adjustment

04/22/2021

71111.15

Corrective Action

Documents

Resulting from

Inspection

4418343

1HK-AF031A, AF Flow Control POT Needs Adjustment

04/22/2021

Corrective Action

Documents

Resulting from

Inspection

25509

NRC Identified: Erroneous ASME Vibration Data

05/25/2021

2BHSR 8.4.2-2

Unit 2 Bus 212 125V Battery Charger Operability

2BOSR 8.6.1-2

25V DC ESF Battery Bank and Charger 212 Operability

Monthly Surveillance (CM-3)

HU-AA-104-101

Procedure Use and Adherence

71111.19

Procedures

MA-BY-723-053

Station Battery Charger 18 Month Surveillance

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

4945435

Clean Battery Charger and Check Connections

04/12/2021

4966367

2 "B" Train 125V Battery Charger Operability Test

04/12/2021

5006411

(Sample/Change) Component Cooling Pump 2B

04/15/2021

5110415

(NEIL)- 2CC01PB Comp IST RQMTS for Residual CC Pump

04/15/2021

26604

1BOSR 5.5.8.SI.5-2A 1B SI IST Group A Pump Test

05/13/2021

Work Orders

5136320

2BOSR 8.6.1-2, 125V Battery & Charger 212 Operability

04/12/2021

Corrective Action

Documents

Resulting from

Inspection

4416813

NRC IDENTIFIED: Residual Boric Acid Leak in Area 7

04/15/2021

Procedures

1BOSR 3.2.8-

2B

Unit One ESFAS Instrumentation Slave Relay Surveillance

(Train B Automatic Safety Injection and RWST LO-2 Level -

K602, K647, K648)

05086672

2B Diesel Generator Operability Run and Semiannual

Surveillance

04/19/2021

4918193

Slave Relay Trn B SI-K602, 647/VA, VC, CV, SI (WK D)

04/21/2021

71111.22

Work Orders

5118448

(NEIL) - 2SI01PB Group A IST Requirements for Safety

Injection

04/15/2021

Miscellaneous

Operations Logs for Selected MSPI

04/01/2020 -

03/31/2021

71151

Procedures

BY-MSPI-001

Reactor Oversight Program MSPI Basis Document

01/30/2020

4416842

NRC Question on DC 211 Ground Status

04/15/2021

4417638

0FP176A Packing Leak

04/19/2021

23476

NRC Identified: 1B SI Pump Window Tags-Plus

05/13/2021

4430576

NRC Identified: 1HK-AF038A has 3% and 5% Indicator

Offset

06/21/2021

Corrective Action

Documents

Resulting from

Inspection

4430638

NRC Identified: Sign Offs Missing in 1AF-018 Loop Cal

Package

06/21/2021

Drawings

M-2037 sh. 1

P&ID/C&I Diagrams Auxiliary Feedwater System-AF

P

Miscellaneous

1AF-018

Auxiliary Feedwater to Steam Generator 1D Flow Control

Loop (AF) (Train B) - Test Report Package (TRP)

1BOL 7.g

LCOAR Auxiliary Feedwater (AF) Flow Control Valves

71152

Procedures

BISR 3.4.2-200

Surveillance Calibration of Aux Feedwater to Steam

Generators A, B, C, and D Flow Control Loops

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Work Orders

4965532

Calibrate Electronic Portion of AF Loop

05/21/2021

21161

TSC Condensing Unit 0VV30C - Compressor 2 Trouble

05/03/2021

27773

0VV30C Comp 1 Trouble

06/06/2021

29603

Annunciator System Trouble

06/16/2021

4430194

1AR12J Spiked into High Alarm

06/18/2021

Corrective Action

Documents

4430661

TSC Condensing Unit 0VV30C - Compressors Tripped

06/21/2021

2BOA ELEC-7

Loss of Annunciators

2BOSR AN-SA1

Annunciator System Input Isolator Circuit Operability

Semiannual Surveillance

BAR 2-4-E7

AN SYS Field Contactor Pwr Trouble

EP-AA-120-1006

EP Reportability - Loss of Emergency Preparedness

Capabilities

71153

Procedures

LS-AA-1110

Safety (SAF) Reportability Manual

31