IR 05000454/2020004

Integrated Inspection Report 05000454/2020004 and 05000455/2020004

ML21027A195
Person / Time
Site:	Byron
Issue date:	01/27/2021
From:	Hironori Peterson Region 3 Branch 3
To:	Rhoades D Exelon Generation Co, Exelon Nuclear
References
IR 2020004
Download: ML21027A195 (25)

Text

January 27, 2021

SUBJECT:

BYRON STATION - INTEGRATED INSPECTION REPORT 05000454/2020004 AND 05000455/2020004

Dear Mr. Rhoades:

On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Byron Station. On January 13, 2021, the NRC inspectors discussed the results of this inspection with Mr. M. Kanavos, 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,

/RA/

Hironori Peterson, Chief Branch 3 Division of Reactor Projects

Docket Nos. 05000454 and 05000455 License Nos. NPF-37 and NPF-66

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000454 and 05000455

License Numbers:

NPF-37 and NPF-66

Report Numbers:

05000454/2020004 and 05000455/2020004

Licensee:

Exelon Generation Company, LLC

Facility:

Byron Station

Location:

Byron, IL

Inspection Dates:

October 1, 2020 to December 31, 2020

Inspectors:

D. Betancourt-Roldan, Senior Resident Inspector

J. Bozga, Senior Reactor Inspector

J. Cassidy, Senior Health Physicist

M. Garza, Emergency Preparedness Inspector

G. Hansen, Sr. Emergency Preparedness Inspector

C. Hunt, Senior Resident Inspector

D. Kimble, Senior Resident Inspector

J. Park, Reactor Inspector

P. Smagacz, Resident Inspector

C. Thompson, Illinois Emergency Management Agency

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 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 75 percent power and was in coast down for a scheduled refueling outage. On October 5, 2020, the unit began a refueling outage. The unit went critical again on October 19, 2020. The unit was returned to full power on October 20, 2020. With the exception of minor reductions in power to support scheduled testing activities, and load changes requested by the transmission dispatcher the unit remained at or near full power 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 Disease 2019 (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; conducted plant status activities as described in IMC 2515, Appendix D, Plant Status; 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 portions 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) (4 Samples)

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

(1) Low temperature over pressure system on October 6, 2020

(2) Fuel pool cooling and cleanup system while defueling on October 8, 2020

(3) Residual heat removal (RH) system while refueling on October 12, 2020 (4)1A Auxiliary Feedwater (AF) train with 2B AF pump out of service for scheduled maintenance on November 12, 2020

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

(1) The inspectors evaluated system configurations during a complete walkdown of the 1B diesel generator (DG) on November 22, 2020.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 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) 12.1-0, fuel handling building, 401' elevation on October 8, 2020

(2) FZ 11.2A-2, 2A RH room on October 12, 2020

(3) FZ 9.2-2, 2A DG and day tank room on October 15, 2020

71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)

(1) The inspectors verified the reactor coolant system boundary, reactor vessel internals, risk-significant piping system boundaries, and containment boundary were appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing documentation for the following activities from October 5, 2020 to October 16, 2020:

03.01.a - Nondestructive Examination and Welding Activities.

• Ultrasonic (UT) and visual (VT) examinations of component 2RC14AD-2 using procedures PDI-UT-2 and ER-AA-335-015-2013

• UT and VT examinations of component 2RC37A-3 using procedures PDI-UT-2 and ER-AA-335-015-2013

• Report No. B2R21-MT-001, Component ID 2RC-01-BA/SGN-02, with relevant indications identified during prior outage accepted for continued service

• Pressure boundary welds 1 and 2 fabricated during elbow replacement on 2SXE5A-3" under Work Order 04826853-01

• Pressure boundary welds 1 and 3 fabricated during repair of 2SXL1AA-4" under Work Order 04899280-01

03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities.

• Liquid penetrant (PT) surface examination of reactor upper head penetrations No. 6 and 68 using procedure ER-AA-335-002

• Bare metal visual (VT) examination of reactor upper head penetrations No. 1, 24, 45, 60 and 76 using procedure ER-AP-335-001

03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.

• Boric Acid Leakage Evaluation of Component ID 2RH8703B, IR 04238047

• Boric Acid Leakage Evaluation of Component ID 2CV8444, IR 04280514

71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance

Requalification Examination Results (IP Section 03.03) (1 Sample)

(1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered from September 17, 2020 to December 4, 2020.

71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)

(1) Biennial Requalification Written Examinations

The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered on November 20, 2020.

Annual Requalification Operating Tests

The inspectors evaluated the adequacy of the facility licensees annual requalification operating test.

Administration of an Annual Requalification Operating Test

The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.

Requalification Examination Security

The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.

Remedial Training and Re-examinations

The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.

Operator License Conditions

The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.

Control Room Simulator

The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.

Problem Identification and Resolution

The inspectors evaluated the licensees ability to identify and resolve problems associated with licensed operator performance.

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)

(1) The inspectors observed and evaluated licensed operator performance in the Control Room during refueling outage U2R22 from October 4 through October 7, 2020, including:

• Shutdown evolutions

• Emergency core cooling system full flow testing

• Reactor head lift

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated licensed operator annual requalification training on November 3, 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)2B AF pump on November 2, 2020

(2) Unit 2 diesel fuel oil transfer system on December 16, 2020

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (2 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 yellow shutdown safety window with pressurizer level < 5 percent and short time to boil on October 6, 2020 (2)2PS9356B is not operable as documented in Action Request (AR) 04377380 on October 18, 2020

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (8 Samples)

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

(1)1B turbine driven feedwater stop valve test as documented in AR 04372705 on October 1, 2020

(2) Nuclear instrument N32 spiking as documented in AR 04374650 on October 6, 2020 (3)2B reactor coolant pump (RCP) oil leaks as documented in AR 04374472 on October 8, 2020

(4) Valve 2SI8807B, will not open as documented in AR 04375187 on October 8, 2020.

(5) Fuel moves suspended due to TRM 3.9a decay time requirements as documented in AR 04375665 on October 10, 2020 (6)2SX02K heat exchanger failed GL 89-13 acceptance criteria as documented in AR 04375807 on October 13, 2020 (7)2DG01KB-X2 lower jacket water cooler leaking 2B DG as documented in AR 04376393 on October 14, 2020

(8) Through wall leak branch leg of tee with lines 1SX311B-6 and 1SXA3A-6 as documented in AR 04392079 on December 30, 2020

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (8 Samples)

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

(1) Valve 2SI8807B will not open as set forth in Work Order (WO) 05085974 on October 13, 2020

(2) TS/Repair 2RH606 valve positioner as set forth in WO 05086643 on October 13, 2020

(3) Valve 2RH610 not functioning in auto as set forth in WO 05084875 on October 13, 2020 (4)2BOSR 5.5.8.CV.5-2A, Group A Inservice Testing (IST) requirements for 2B charging pump 2CV01PB, revision 12, following maintenance on October 14, 2020 (5)2B AF pump as set forth in WO 4649471 following maintenance on October 15, 2020 (6)2B RCP following repair on October 14, 2020

(7) SPP-20-016, Ovation U2 N-Outage MAT, Revision 0 on October 15, 2020

(8) Low power physics testing as set forth in WO 04915374 on October 19, 2020

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated refueling outage U2R22 activities from October 5 through October 24, 2020.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) Main steam safety valve operability test as set forth in WO 04911628 on October 2, 2020

(2) Local leak-rate test (LLRT) for P-47; 2RF026, 2RF027, and 2RF055 as set forth in WO 0491196 on October 13, 2020

71114.02 - Alert and Notification System Testing

Inspection Review (IP Section 02.01-02.04) (1 Sample)

(1) The inspectors evaluated the following maintenance and testing of the alert and notification system:

• Annual siren inspection and maintenance records for the period from September 2018 to September 2020.

• Monthly alert notification system (siren) tests for the period from September 2018 to September 2020.

71114.03 - Emergency Response Organization Staffing and Augmentation System

Inspection Review (IP Section 02.01-02.02) (1 Sample)

(1) The inspectors evaluated the readiness of the Emergency Preparedness Organization.

71114.04 - Emergency Action Level and Emergency Plan Changes

Inspection Review (IP Section 02.01-02.03) (1 Sample)

(1) The inspectors completed an evaluation of submitted emergency action level and emergency plan changes on December 2, 2020. This evaluation does not constitute NRC approval.

71114.05 - Maintenance of Emergency Preparedness

Inspection Review (IP Section 02.01 - 02.11) (1 Sample)

(1) The inspectors evaluated the maintenance of the emergency preparedness program.

71124.01 - Radiological Hazard Assessment and Exposure Controls

Instructions to Workers (IP Section 03.02) (1 Partial)

(1)

(Partial)

The inspectors evaluated radiological protection-related instructions to plant workers.

However, the completion of the sample requires direct inspector observations which could not be performed due to COVID-19 restrictions.

71124.04 - Occupational Dose Assessment

Source Term Characterization (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.

External Dosimetry (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated licensee performance as it pertains to external dosimetry that is used to assign occupational dose.

Internal Dosimetry (IP Section 03.03) (1 Sample)

The inspectors evaluated the following internal dose assessments for actual internal exposures:

(1) Dose assessment for an individual potentially exposed to airborne radioactivity during temporary ventilation system malfunction in the Unit 1 containment on March 14, 2020.

Special Dosimetric Situations (IP Section 03.04) (1 Sample)

The inspectors evaluated the following special dosimetric situations:

(1) Effective Dose Equivalent for External Exposures related to Control Rod Drive Mechanism (CRDM) Inspections on Radiation Work Permit (RWP) BY-1-20-0067 (Task 1).

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

EP01: Drill/Exercise Performance (IP Section 02.12)===

(1) January 1, 2019 - June 30, 2020

EP02: ERO Drill Participation (IP Section 02.13) (1 Sample)

(1) January 1, 2019 - June 30, 2020

EP03: Alert & Notification System Reliability (IP Section 02.14) (1 Sample)

(1) January 1, 2019 - June 30, 2020

BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)

(1) Unit 1 (October 1, 2019 - September 30, 2020)

(2) Unit 2 (October 1, 2019 - September 30, 2020)

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) April 2019 - September 2020

71152 - Problem Identification and Resolution

Semiannual Trend Review (IP Section 02.02) (1 Sample)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends in GL 89-13 heat exchanger (HX) failures that might be indicative of a more significant safety issue on November 10, 2020.

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

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) RCCA R785 has a bent rodlet as documented in IR 04375784 on October 16,

INSPECTION RESULTS

Observation: Rod Cluster Control Assembly R785 has a bent rodlet 71152 On October 10, 2020, during insert shuffles in support of the Unit 2 refueling outage, while attempting to insert a Rod Cluster Control Assembly (RCCA) into the host assembly the crew observed a rodlet bending and immediately stopped the evolution. The licensee inspected the affected RCCA and made the decision to remove it from service. The licensee performed inspections of the RCCA tool visually and functionally, as well as the associated fuel assemblies, and did not identify any additional issues. After inspections were completed, the licensee resumed transferring the other 24 RCCAs without incident, including a replacement for the damaged RCCA.

In conjunction with the fuel vendor, the licensee chose a suitable RCCA for replacement after evaluating the available RCCAs in the spent fuel pool. The evaluation included mechanical integrity testing, to include a visual inspection and a drag test. The fuel vendor also performed an engineering evaluation to support the lifetime extension of the chosen RCCA for one additional refueling cycle. The evaluation included an evaluation of swelling, mechanical wear, risk of potential manufacturing issues, and corrosion. The vendor concluded that the chosen RCCA was an acceptable replacement for use provided it not be used in a shutdown bank, the RCCA be parked at 231 steps or at 225 steps for the upcoming cycle, and that the exposure for the RCCA does not exceed 16 effective full power years.

On November 22, 2020, while performing training with a dummy fuel assembly and dummy RCCA, the licensee observed a similar bending of a rodlet while lowering the RCCA into the assembly. The licensee removed the RCCA tool from service pending an investigation of the tool by the vendor.

The inspectors reviewed the corrective action program (CAP) causal evaluation performed by the licensee for the initial occurrence of the rodlet bending during insert shuffles. The inspectors determined that the actions taken by the licensee were commensurate with the safety significance of the issue and in accordance with site procedures. The inspectors reviewed the engineering evaluation on the replacement RCCA chosen from the spent fuel pool and concluded that there is reasonable assurance that the replacement RCCA will perform as required for the upcoming cycle. At the time of this report, the investigation of the RCCA tool by the vendor is scheduled to be complete in February of 2021 and is being tracked in the licensee's CAP.

The inspectors did not identify any findings or violations during this inspection sample.

Observation: Generic Letter 89-13 Heat Exchanger Inspection Failures 71152 Inspectors performed a semi-annual trend review of as-found heat exchanger inspections performed by the licensee between May 1, 2020, and December 15, 2020. Inspections were performed in accordance with licensee procedure BVP 800-30, Essential Service Water Fouling Monitoring Program, which is the licensee's Generic Letter (GL) 89-13 program basis document and identifies the procedures and methodology used to control and monitor fouling of the safety related service water system piping, components, and heat exchangers at Byron in accordance with the licensees official response to NRC. Over this time period, the licensee performed seven as-found heat exchanger inspections. Of the seven inspections, five inspections failed to meet the acceptance criteria for tube blockage and were entered in the CAP as listed below:

• AR 04343226 2SX01AB HX Failed GL 89-13 Acceptance Criteria on May 14, 2020;

• AR 04349085 2SX01AA HX Failed GL 89-13 Acceptance Criteria on June 09, 2020;

• AR 04370066 1SI01SB HX Failed GL 89-13 Acceptance Criteria on September 17, 2020;

• AR 04375807 2SX02K HX Failed GL 89-13 Acceptance Criteria on October 10, 2020; and

• AR 04387841 2SX01AA As found Heat Exchanger Inspection on December 03, 2020.

The inspectors reviewed the past operability evaluation performed by the licensee for each as-found heat exchanger inspection failure. The inspectors determined that in each case, the licensee provided reasonable assurance that the safety related components supported by each heat exchanger would have been able to perform their safety functions as required during a design basis accident.

During their review, inspectors reviewed GL 89-13 inspections from previous years on the heat exchangers listed above to determine if an adverse trend existed. Inspectors noted that the 2A essential service water pump lube oil cooler (2SX01AA) has failed six out of its last seven GL 89-13 heat exchanger inspections since 2016. The 2B essential service water pump lube oil cooler (2SX01AB) has failed two out of three GL 89-13 heat exchanger inspections since 2016. The acceptance criteria for tube blockage on the 2SX01AA and 2SX01AB heat exchangers, as determined by Byron calculation BYR03-115 (EC 628987), is no greater than four total blocked tubes.

ER-AA-340-1001, "GL 89-13 Program Implementation Instructional Guide," states, in part, that the licensee should evaluate past heat exchanger cleaning and inspection frequency against as found conditions to determine if the frequency is adequate. Additionally, the licensee should document the justification for the chosen frequency of cleaning and inspecting to ensure that the heat removal requirements for the system are satisfied. Based on the inspectors review of previous GL 89-13 inspections, the licensees practice is to reduce the inspection frequency by one half upon a failure to meet the acceptance criteria for tube blockage (e.g., from two years to one year). The current inspection frequency for 2SX01AA is every six months while the inspection frequency for 2SX01AB is every year.

The inspectors reviewed the most recent licensee evaluation of the inspection frequencies for both heat exchangers after their respective inspection failures. In both cases, the licensee determined that the heat exchanger inspection frequencies would remain unchanged. The licensee highlighted previous engineering calculations concerning the heat removal capability of the coolers and noted that reducing the frequency further would increase unavailability on a mitigating system perform index (MSPI) related train in order to perform the inspections.

Inspectors noted that one particular GL 89-13 inspection failure captured under AR 02735109 on October 31, 2016, documented a failed inspection for the 2SX01AA heat exchanger in which five tubes were fully blocked and seven tube were partially blocked on the inlet/outlet tube side, and seven tubes were found fully blocked and four tubes were partially blocked on the reversing end of the heat exchanger. The licensee performed an evaluation of the condition under Engineering Change (EC) 617320 and determined that lube oil temperatures would have remained acceptable under design basis conditions even with the reported tube blockage.

Following the condition evaluated in AR 02735109, programmatically driven evaluations performed by the licensee for subsequent inspection failures have continuously highlighted EC 617320 as justification for why exceeding the tube plugging limit in BYR03-115 would not have challenged the safety function of the essential service water (SX) pump. Additionally, the licensee has also repeatedly highlighted an evaluation performed at the Braidwood Station of a similar condition deemed acceptable under EC 619171. The Byron and Braidwood Station essential service water pumps are a similar design.

On February 12, 2019, the licensee completed a GL 89-13 program self-assessment. An action from that assessment was generated in the CAP under AR 04136180-11 for the site to determine if the essential service water pump lube oil coolers could be removed from the GL 89-13 program based on previous EC evaluations. The licensee stated that preliminary information received from the vendor verified that the oil coolers heat exchanging properties are not required for SX pump bearing health and that eliminating the oil coolers would be acceptable for normal and accident operation. The due date for this action item, however, has been pushed to March 25, 2022, awaiting the final decision on the permanent shutdown of Byron Station.

Specifically concerning the 2SX01AA and 2SX01AB heat exchangers, the inspectors determined that by waiting to evaluate whether the heat exchangers can be removed from the GL 89-13 program until March 25, 2022, combined with not taking any additional programmatic actions for GL 89-13 inspection failures, the licensee appears to be creating a de facto alternate set of acceptance criteria by which the heat exchangers are being evaluated against after an inspection failure occurs. In doing this, the licensee has set up a rear looking program in which there is a presumption that any failure to meet the acceptance criteria given in BYR03-115 will be acceptable because EC 617320 will justify past operation of the heat exchanger, given a certain amount of tube blockage, and therefore the safety related function of the components supported by each heat exchanger will have been preserved. As such, by entering each inspection failure into the CAP and generating actions to perform programmatic evaluations the licensee is meeting the requirements of BVP 800-30; however, without taking action to either change the acceptance criteria, change the inspection frequency, or justify the exclusion of the heat exchangers from the program, the likely outcome is that the whole scenario will repeat itself upon the next inspection failure. This practice has the potential to put an undue strain on site resources and can reduce the sites focus on other safety significant work.

The inspectors did not identify any findings or violations during this sample.

EXIT MEETINGS AND DEBRIEFS

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

• On January 13, 2021, the inspectors presented the integrated inspection results to Mr. M. Kanavos, Site Vice President, and other members of the licensee staff.

• On October 2, 2020, the inspectors presented the emergency preparedness baseline inspection results to Mr. M. Kanavos, Site Vice President, and other members of the licensee staff.

• On October 16, 2020, the inspectors presented the Inservice Inspection results to Mr. Harris Welt, Plant Manager, and other members of the licensee staff.

• On October 26, 2020, the inspectors presented the radiation protection inspection results to Mr. J. Reed, Radiation Protection Manager, and other members of the licensee staff.

• On December 2, 2020, the inspectors presented the emergency action level and emergency plan changes inspection results to Mr. D. Moore, Senior Manager - Emergency Preparedness, and other members of the licensee staff.

• On December 8, 2020, the inspectors presented the biennial licensed operator requalification program inspection results to Mr. K. McGuire, Operations Director, and other members of the licensee staff.

• On December 10, 2020, the inspectors presented the radiation protection inspection results to Mr. J. Reed, Radiation Protection Manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71111.04

Procedures

BOP AF-E2A

Auxiliary Feedwater Train A Electrical Lineup

BOP AF-M2

Auxiliary Feedwater System Valve Lineup

BOP AF-M2A

Auxiliary Feedwater System Train A Valve Lineup

BOP FC-E1

Fuel Pool Cooling - Electrical Lineup

BOP FC-M1

Fuel Pool Cooling and Cleanup System Valve Lineup

71111.05

Fire Plans

FZ 1.2A-2

Aux Building 346'0" ELE. 2A RHR Pump Room

FZ 12.1-0

Fuel Handling Building 401'-0" Elevation

FZ 9.2-2

Aux Building 401'0" Elevation 2A Diesel Generator & Day

Tank Room

71111.08P

Corrective Action

Documents

238047

Boric Acid Leakage Evaluation for Component ID

2RH8703B

04/19/2020

238994

Indications Observed During ISI Exam of 2RC-01-BA/SGN-

04/12/2019

280514

Boric Acid Leakage Evaluation for Component ID 2CV8444

10/14/2019

04362874

B2R22 ISI Scope Deferred Due to Ongoing COVID-19

Pandemic

08/13/2020

Corrective Action

Documents

Resulting from

Inspection

04374742

Incorrect NDE Report # Entered in B2R21 WO# 04826853-

WDR

10/06/2020

Miscellaneous

1-53B

Procedure Qualification Record (PQR)

01/29/1986

2-53A

Procedure Qualification Record (PQR)

2/12/1986

WPS 1-1-GTSM-

PWHT

ASME Welding Procedure Specification Record

WPS 1-8-GTSM

ASME Welding Procedure Specification Record

NDE Reports

2019-034

03/20/2019

2019-035

03/20/2019

2019-036

03/20/2019

2019-037

03/21/2019

2019-039

03/21/2019

2019-MT-012

04/13/2019

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

2019-MT-013

04/13/2019

20-UT-047

10/07/2020

20-VT-010

10/07/2020

B2R22-PT-001

10/08/2020

B2R22-PT-002

10/08/2020

B2R22-UT-001

10/07/2020

B2R22-VEN-001

Reactor Vessel Head Bare Metal Visual Examination Record 10/11/2020

B2R22-VT-001

10/07/2020

Procedures

Guidance for Performing Thermal Fatigue Examinations

When Utilizing Generic Procedure PDI-UT-2

ER-AA-335-002

Liquid Penetrant (PT) Examination

ER-AA-335-015-

2013

VT-2 Visual Examination in Accordance with ASME 2013

Edition

ER-AA-335-031

Ultrasonic Examination of Austenitic Piping Welds

ER-AP-335-001

Bare Metal Visual Examination for Nickel Alloy Materials

PDI-UT-2

Generic Procedure for the Ultrasonic Examination of

Austenitic Pipe Welds

H

PDI-UT-2 Table 1

PDI-UT-2 Table 2

03/04/2020

Work Orders

04826853-01

MM Repair Leak by Replacing Elbow

04/13/2019

04899280-01

MM - Potential Inactive Leak on 2SXL1AA-4" Line

04/04/2019

71111.11B

Corrective Action

Documents

AR 04189569

4.0 Critique FOR 2FW-541A Failure

10/30/2018

AR 04209528

4.0 Critique for U-1 Main Condenser Vacuum Degrading -

Prompt Investigation and Site Communication Actions Will

be Performed Under IR 4209128

01/09/2019

AR 04273574

4.0 Critique - 2C MSIV Standby Actuation Train Leak

08/21/2019

AR 04317378

4.0 Critique - EH Return Filter Response

2/12/2020

AR 4341834

Trend in HU Fundamental Usage in Operations (CAPE)

06/12/2020

Corrective Action

Documents

Resulting from

Inspection

AR 04384222

Simulator Set-up Procedure TQ-BY-201-0113 Was Not

Followed, Challenging LORT Exam Security During the

Annual Exam

11/16/2020

SWR 0136543

Simulator Work Request (SWR) Written to Investigate

Status Lights on 1PM04J. When the Valves were Closed the

11/18/2020

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Light Needed Tapping to Light and Show That Valves Were

Closed.

Miscellaneous

20 JPM Wk 1

20 Byron Annual Operating Test Week 1 Job

Performance Measures (N001a, N019, N089a, N136, N144,

S033t)

06/12/2020 -

06/22/2020

20 JPM Wk 5

20 Byron Annual Operating Test Week 5 Job

Performance Measures (N042, N046, N088, N128a, N147a,

S035t)

06/15/2020 -

06/23/2020

20 Op-Test

Outline

20 Byron Annual Operating Test Outline

11/09/2020

20 Scn Wk 1

20 Byron Annual Operating Test Week 1 Scenarios

(BY-59R3, BY-70R3)

09/09/2020

20 Scn Wk 5

20 Byron Annual Operating Test Week 5 Scenarios

(BY-44R7, BY-73R9)

06/09/2020

JPM N147a

LORT Annual Exam JPM Performed 11/17/2020 in the

Simulator

6/22/2020

NRC FORM 396

Reviewed 6 Medical Records (3 RO and 3 SRO) to Assess

Compliance with 10CFR55.53 and Medical Fitness

2/2019

OP-AA-105-102,

ATTACHMENT 1

Several Active License Tracking Logs (Record of 8 / 12 Hour

Shifts Worked During Quarter) to Assess the Licensees

Program for Ensuring that Licensed Operators Meet the

Conditions of their Licenses

TQ-AA-224-F100

Reviewed 15 Individual "Remedial Training Notification and

Action on Failure" Forms for LORT Remediations Performed

from 2018 to 2020

- 8

TQ-AA-306-J002

Test Report Documenting the Simulator's Testing

Completed Since the Previous Report on 11/5/2018

Documenting Conformance to the Requirements of ANSI 3.5

2009 and Regulatory Guide 1.149 Revision 4

Vision ID 337340

20 Week 5 Biennial SRO Written Exam

11/11/2020

Vision ID 342306

20 Week 5 Biennial RO Written Exam

11/06/2020

Procedures

TQ-AA-150-J202

LORT Annual Exam Development Job Aid

005

TQ-AA-155

Conduct of Simulator Training and Evaluation

010

TQ-AA-201

Examination Security and Administration

017

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

TQ-BY-201-0113,

1,

PRE - Simulator

Examination

Security Checklist

The Examination Security Checklist That Was Not

Performed Properly, Resulting in the Exam Security

Challenge Documented by AR 4384222 and Subsequent

Reviews

11/12/2020

71111.11Q Miscellaneous

Operations Scenarios

11/03/2020

71111.12

Procedures

ER-AA-320

Maintenance Rule Implementation Per NEI 18-19

71111.13

Corrective Action

Documents

04375187

2SI8807B Will Not Open

10/08/2020

04377380

2PS9356B is Not Operable

10/17/2020

Engineering

Changes

EC367380

Documentation of the Basis for Maximum Allowed Leakage

Rate in Procedures 1/2BVSR 6.1.1-26

Miscellaneous

Penetration/Valve:

P-70, 2PS9356B

Containment Boundary Repair Deferral Form

10/17/2020

71111.15

Calculations

BYRON-00-5043

Generic Jacket Water Leakage Evaluation for Emergency

Diesel Generators

06/02/2000

EC623441

Design Attribute Review CC-AA-102-F-01

Corrective Action

Documents

04372705

1B TDFW Pump Stop Valve Test Failure

09/28/2020

04373650

N32 Spiking

11/05/2020

04374472

2B RCP Oil Leaks

10/05/2020

04375187

2SI8807B Will Not Open

10/08/2020

04375665

TRM 3.9A, Decay Time Requirements and Fuel Moves

10/09/2020

04375807

2SX02K HX Failed GL 89-13 Acceptance Criteria

10/10/2020

04376393

2DG01KB-X2 LWR JKT Water Cooler Leaking 2B DG

10/13/2020

04392079

Through Wall Leak Branch Leg of Tee with Lines 1SX211B-

6" & 1SXA3A=6"

2/25/2020

Engineering

Changes

633450

Operability Evaluation 20-002

EC357755

Past Operability Evaluation for 2B AF Pump Right Angle

Gear Lube Oil Cooler - 2SX02K

Procedures

ER-AA-340-1001

GL 89-13 Program Implementation Instructional Guide

71111.19

Corrective Action

Documents

04374416

2RH610 Not Functioning in Auto

10/05/2020

04375187

2SI8807B Will Not Open

10/08/2020

04375247

2RH606 is Not Full Open

10/08/2020

04375488

2RH606 Valve Control Issue

10/09/2020

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Procedures

04375187

2SI8807B Will Not Open

10/08/2020

NF-BY-510

Low Power Physics Testing

SFP-20-016

Ovation U2 N-Outage MAT

Work Orders

04915374

Low Power Physics Testing

10/19/2020

04942198

EWP MM: 2CV01PB Repair Inboard Bearing Housing Oil

Leak

10/09/2020

05084875

EWP IM Troubleshoot 2FIS-0610

10/10/2020

05085974

2SI8807B Will Not Open

10/09/2020

4649471

Replace 2B AF Pump Outboard Seal and PMT

10/14/2020

4948255

Unexpected Alarm: 2B RCP Upper Oil Reservoir

10/09/2020

71111.20

Engineering

Evaluations

BY-MODE-030

TS 3.0.4.B Evaluation - Mode Change with Technical

Specifications Equipment Out of Service

Procedures

2BGP 100-2A1

Reactor Startup

BOP PC-1T1

Unit 1/2 - Containment Closure Verification Checklist

71111.22

Procedures

2BOSR 6.1.1-18

Unit 2 Primary Containment Type C Local Leakage Rate

Tests and IST Tests of Containment Floor Drains System

BVP 800-39

Byron Containment Leakage Rate Testing Program

ER-AA-380

Primary Containment Leakrate Testing Program

Work Orders

0491196

Main Steam Safety Valves Operability Tests

10/02/2020

71114.02

Corrective Action

Documents

AR 04269605

EP-Siren Failure (BY17)

08/05/2019

AR 04271146

EP-Siren Failure (BY53)

08/12/2019

AR 04271957

EP-Siren Failure (BY05)

08/14/2019

AR 04279867

EP-Siren Failure (BY02)

09/17/2019

AR 04294772

EP-Siren Failure (BY53)

11/05/2019

AR 04308190

EP-Siren Failure (BY02)

01/06/2020

AR 04344000

EP-Siren Failure (BY59)

05/18/2020

AR 04345690

EP-Siren Failure (BY27)

05/26/2020

Miscellaneous

Exelon Nuclear Manager, Midwest Emergency

Preparedness Letter to Program Enhancement Manager,

Illinois Emergency Management Agency; Submission of

Byron Generating Station Public Alert and Notification

System (ANS) Design Report, Revision 3

10/01/2018

Byron Station 2018 Warning System Maintenance &

01/01/2018 -

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Operational Reports

2/31/2018

Byron Station 2019 Warning System Maintenance &

Operational Reports

01/01/2019 -

2/31/2019

Byron Station 2020 Warning System Maintenance &

Operational Reports

01/01/2020 -

2/31/2020

Byron Station Monthly Siren Availability Reports

09/01/2018 -

08/31/2020

Byron Station Siren Corrective Maintenance Reports

09/01/2018 -

08/31/2020

2019/2020 Emergency Planning for the Byron Area

(Community Information Booklet)

7/19/2019

U.S. Department of Homeland Security, FEMA Letter;

Backup Alert and Notification System

2/10/2012

KLD-TR-986

Byron Generating Station Alert and Notification System

(ANS) Design Report

09/19/2018

Procedures

EP-AA-1000

Exelon Nuclear Standardized Radiological Emergency Plan

Section E

EP-AA-1002

Exelon Nuclear Radiological Emergency Plan Annex for

Byron Station, Section 4

71114.03

Corrective Action

Documents

294834

Byron EP Unannounced ERO Augmentation Call in Drill

Results

10/26/2019

AR 04304810

Annual Test of ERO Back-Up Notification System

2/18/2019

AR 04323634

ERO Vacancy - Replacement Needed

03/04/2020

Miscellaneous

Quarterly Unannounced Off-Hours Call-In Augmentation Drill

Results

09/01/2018 -

08/31/2020

Emergency Response Organization Duty Team Roster

08/31/2020

ERO Staff Training Records Review (Sample - 10)

Procedures

EP-AA-1000

Exelon Nuclear Standardized Radiological Emergency Plan,

Sections B and N

EP-AA-1000,

Appendix 5

ERO Staffing and Augmentation

EP-AA-1002

Exelon Nuclear Radiological Emergency Plan Annex for

Byron Station, Section 2

EP-AA-1002

Exelon Nuclear Radiological Emergency Plan Annex for

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Byron Station, Addendum 1, On-Shift Staffing Technical

Basis

EP-AA-112-100-

F-06

ERO Notification or Augmentation

X

EP-AA-112-200

TSC Activation and Operation

EP-AA-112-300

OSC Activation and Operation

EP-AA-112-400

EOF Activation and Operation

EP-AA-120-F-02

EP Staff Initial Developmental Checklist

H

TQ-AA-113

ERO Training and Qualification

71114.04

Corrective Action

Documents

IR 4325295

Perform Impact Review of EAL Revisions for EOP/SAMG

03/10/2020

IR 4328154

EP FAQ EAL Change License Amendment Implementation

Actions

03/20/2020

IR 4329864

NOS ID: Revise Standardized Emergency Plan

03/26/2020

IR 4334253

EPlan: CDAM 50.54(q) Potential Deficiencies

04/09/2020

Miscellaneous

Eval No. 19-29

Exelon Nuclear Standardized Radiological Emergency Plan

09/04/2019

Eval No. 19-65

Exelon Nuclear Standardized Radiological Emergency Plan

09/06/2019

Eval No. 19-79

Various Station Emergency Plan Annexes

11/08/2019

Eval No. 19-80

On-Shift Staffing Assessments

11/08/2019

Eval No. 20-25

EALs for Byron Station

06/04/2020

71114.05

Corrective Action

Documents

AR 04183230

EP Benchmark Recommendation #1

10/13/2018

AR 04249481

EMNET Phone Issues

05/13/2019

AR 0428273

Byron EP Dixon Alt Facility - Supplies Missing

09/27/2019

AR 04303221

NRC Red Phone Not Working in Main Control Room

2/12/2019

AR 04309602

MET Tower 250 Ft. Wind Speed Instrument Failure

01/10/2020

AR 04321869

EP OSC Inventory Issue

2/26/2020

AR 04338733

NRC ENS (Red) Phone Not Working

04/27/2020

AR 04339367

Outdated URI Software Found on Three TSC Computers

04/29/2020

AR 04341130

EP CFAM Indicators - 3 Month Decline - March

05/05/2020

AR 04342423

Byron NRC FTS Phones Will Not Ring in the TSC

05/11/2020

AR 04353687

Byron 2020 HP Drill - Lessons Learned

06/12/2020

AR 04359810

NRC (ENS) Red Phone Not Working in Main Control Room

07/30/2020

Corrective Action

Documents

AR 04373275

NRC ID - Inventory Observations

09/30/2020

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Resulting from

Inspection

Miscellaneous

EP-MW-124-

1001-F-01

Control Room/Simulator Inventory Records

10/01/2018 -

06/30/2020

EP-MW-124-

1001-F-02

CR/Simulator/TSC/OSC Equipment Test - TSC Software

and Reference Document Inventory Records

10/01/2018 -

06/30/2020

EP-MW-124-

1001-F-03

Technical Support Center Inventory Records

10/01/2018 -

06/30/2020

KLD-TR-1001

Byron Generating Station 2018 Population Update Analysis

07/05/2018

KLD-TR-1081

Byron Generating Station 2019 Population Update Analysis

09/07/2019

KLD-TR-1180

Byron Generating Station 2020 Population Update Analysis

09/05/2020

KLD-TR-637

Evacuation Time Estimates for Byron Station Plume

Exposure Pathway Emergency Planning Zone

Procedures

EP-AA-1000

Exelon Nuclear Standardized Radiological Emergency Plan

Section J, Protective Response

EP-AA-1002

Exelon Nuclear Radiological Emergency Plan Annex for

Byron Station, Section 3, Classification of Emergencies

EP-AA-1002

EP-AA-1002; Exelon Nuclear Radiological Emergency Plan

Annex for Byron Station, Section 5.1, Emergency Response

Facilities

EP-AA-1002,

Addendum 3

Emergency Action Levels for Byron Station

EP-AA-122

Drills and Exercise Program

71124.01

ALARA Plans

BY-2-20-00613

Rx Head Dis-Assembly / Re-Assembly

09/26/2020

BY-2-20-00623

Rx Cavity Decontamination - TASK 1 / 2

09/29/2020

Radiation Work

Permits (RWPs)

BY-2-20-00513

Aux / Containment RP Activities

71124.04

Corrective Action

Documents

AR 04326700

Containment Evacuation Required Due to Airborne

Radiation

03/14/2020

Miscellaneous

BYR-20-002

20 Bioassay Program Annual Review at Byron Nuclear

Power Station

NCS-19-002

Removing SRD/DLR Bias

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

NVLAP Lab Code

100518-0

Certificate of Accreditation to ISO/IEC 17025:2005

01/01/2020 -

2/31/2020

Project ID#

EX001-

3P61BYRON-05

Report of Analysis/Certificate of Conformance

09/23/2019

RP-AA-210-1001

13

EID KRAME4049

Multiple Dosimetry EDE Evaluation Sheet

03/12/2020

RP-AA-220

EID Garci8849

Intake Investigation Form and Supporting Documents

03/24/2020

RP-AA-302

Alpha Area Level Assessment - Unit 1

07/05/2020

RP-AA-403

RWP BY-0-19-

00305

Planned Dose Rate Alarm Form

10/04/2019

Teledyne Brown

Engineering

Project ID#

EX001-

3P61BYRON-05

Report of Analysis/Certificate of Conformance

09/23/2019

Procedures

NISP-RP-003

Radiological Air Sampling

RP-AA-210

Dosimetry Issue, Usage, and Control

RP-AA-222

Methods for Estimating Internal Exposure from In Vivo and

In Vitro Bioassay Data

Radiation

Surveys

20-066849

B/C Steam Generator Platform

03/12/2020

Radiation Work

Permits (RWPs)

BY-1-20-00608

Rx Head and Vessel Internal ISI (Bare Metal Exam)

Self-Assessments AR 4198147

Radiation Protection Dosimetry - Exelon Stations

11/20/2019

71151

Miscellaneous

RCS Data 10/01/2019 - 09/30/2020

LS-AA-2140

Monthly Data Elements for NRC Occupational Exposure

Control Effectiveness

April 2019 -

September

20

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

71152

Calculations

BYR03-115 (EC 28987)

SX Pump Oil Cooler Allowable Tube Blockage

EC339308

Acceptance Criteria for As-Found Heat Exchanger Tube

Blockage

EC357755

Past Operability Evaluation for 2B AF Pump Right Angle

Gear Lube Oil Cooler-2SX02K

EC617320

Reportability Evaluation for 2A SX Pump Oil Cooler Silting

EC619171

Review of Calculation BRW-95-218 for Application to

Identified Low Flow Condition on SX Oil Cooler

Corrective Action

Documents

04083000

2SX01AA Heat Exchanger Failed GL 89-13 Inspection

2/11/2017

230570

2SX01AB HX Failed GL 89-13 Acceptance Criteria

03/18/2019

245333

2SX01AA HX Failed GL 89-13 Acceptance Criteria

05/01/2019

04302832

2SX01AA HX Failed GL 89-13 Acceptance Criteria

2/10/2019

04349085

2SX01AA HX Failed GL 89-13 Acceptance Criteria

06/04/2020

04375785

RCCA R785 Has a Bent Rodlet

10/10/2020

04379007

Bent RCCA Rodlet

10/23/2020

Engineering

Changes

EC390906

Past Operability Evaluation for the 1B SI Pump

Engineering

Evaluations

NF-CB-30-150

Review of RCCA R609 at Byron Unit 2

10/16/2020

Procedures

BVP 800-30

Essential Service Water Fouling Monitoring Program (GL 89-13 Program Basis Document)

ER-AA-340-1001

GL 89-13 Program Implementation Instructional Guide

ER-AA-340-1002

Service Water Heat Exchanger Inspection Guide

Self-Assessments 4136180

GL 89-13 Triennial Ultimate Heat Sink Inspection

2