IR 05000454/2018001

NRC Integrated Inspection Report 05000454/2018001; 05000455/2018001 and ISFSI Cask Loading Inspection Report 07200068/2018001

ML18127A897
Person / Time
Site:	Byron
Issue date:	05/07/2018
From:	Eric Duncan Region 3 Branch 3
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
References
IR 2018001
Download: ML18127A897 (16)

Text

UNITED STATES May 7, 2018

SUBJECT:

BYRON STATION, UNITS 1 AND 2NRC INTEGRATED INSPECTION REPORT 05000454/2018001; 05000455/2018001 and ISFSI CASK LOADING INSPECTION REPORT 07200068/2018001

Dear Mr. Hanson:

On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed a quarterly integrated inspection at your Byron Station, Units 1 and 2. On April 18, 2018, the NRC inspectors discussed the results of this inspection with Mr. M. Kanavos and other members of your staff. The results of this inspection are documented in the enclosed report.

The NRC did not identify any findings of significance during this inspection period.

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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Eric Duncan, Chief Branch 3 Division of Reactor Projects Docket Nos. 50-454; 50-455; 72-68 License Nos. NPF-37; NPF-66 Enclosure:

IR 05000454/2018001; 05000455/2018001; 0720068/2018001 cc: Distribution via LISTSERV

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance by conducting an integrated quarterly inspection at Byron Station Units 1 and 2 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. The NRC and self-revealed findings, violations, and additional items are summarized in the table below.

List of Findings and Violations No findings or violations were identified.

Additional Tracking Items Type Issue Number Title Report Status Section URI 05000454/2016001-01; Failure to Enter Technical 71111.15 Closed 05000455/2016001-01 Specification Limiting Condition for Operation Action Requirement with Auxiliary Feedwater Flow Control Valves Failed Open

PLANT STATUS

Byron Unit 1 operated at scheduled power levels for the entire inspection period.

Byron Unit 2 operated at scheduled power levels 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 performed plant status activities described in IMC 2515 Appendix D, Plant Status and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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.

REACTOR SAFETY

71111.01Adverse Weather Protection Impending Severe Weather

The inspectors evaluated readiness for impending adverse weather conditions for a winter storm warning issued by the National Weather Service on February 8, 2018.

External Flooding (1 Sample)

The inspectors evaluated readiness to cope with external flooding on February 21, 2018, after a flood warning was issued for the Rock River.

71111.04Equipment Alignment Partial Walkdown

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

(1) Unit 2 condensate and condensate booster pumps after gear box maintenance and pump realignment on January 26, 2018;

(2) 2B diesel generator (DG) while 2A DG was in maintenance on January 31, 2018;

(3) Essential service water (SX) pumps with 1A SX pump out-of-service for maintenance on February 7, 2018; and

(4) Unit 2 safety-related 125 volts-direct current (VDC) batteries and battery chargers on

===February 14, 2018.

Complete Walkdown (1 Sample)===

The inspectors evaluated system configurations during a complete walkdown of the Unit 2 diesel fuel oil supply system on March 2, 2018.

71111.05AQFire Protection Annual/Quarterly Quarterly Inspection

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Fire Zone 5.4-2, Division 22 miscellaneous electrical equipment and battery room on January 9, 2018;

(2) Fire Zone 18.3-1, Unit 1 main steam and auxiliary feedwater pipe tunnel on January 18, 2018;

(3) Fire Zone 10.1-1, 1B diesel fuel oil storage tank on January 30, 2018;

(4) Fire Zone 8.6-0, turbine building 451 elevation on February 16, 2018; and

(5) Fire Zone 8.5-0, turbine building 426 elevation on March 15, 2018.

71111.06Flood Protection Measures Internal Flooding

(1) The inspectors evaluated internal flooding mitigation protections in the Unit 1 auxiliary feedwater (AF) pipe tunnel on January 18, 2018; and

(2) The inspectors evaluated internal flooding mitigation protection in the safety-related equipment areas of the 380 and 401 elevations of the auxiliary building that were accessed from the turbine building, including diesel generator room barriers and watertight doors to diesel oil storage tanks rooms on January 30, 2018.

71111.07Heat Sink Performance Heat Sink

The inspectors evaluated 2A DG jacket water heat exchanger inspection on January 29, 2018.

71111.11Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification

The inspectors observed and evaluated a crew of licensed operators in the plants simulator during licensed operator requalification training on March 6, 2018.

Operator Performance (1 Sample)

The inspectors observed and evaluated the on shift crew during a control room observation on March 8, 2018.

71111.12Maintenance Effectiveness Routine Maintenance Effectiveness

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) Function SI-07, Unit 1 safety injection system.

Quality Control (1 Sample)

The inspectors evaluated maintenance and quality control activities associated with the following equipment performance issue:

(1) Function DC-02, Unit 2 125 VDC power, on February 14, 2018. The licensee documented a trip of the 212 battery charger in AR 04063154, B2R20M4 212 Battery Charger Input Breaker Tripped Open 2BOSR 8.1.11-2. The failure was attributed to a failure of the sensing and current limiting circuit board.

71111.13Maintenance Risk Assessments and Emergent Work Control

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) Repair of through-wall leak on spent fuel cooling pipe 0FC03B-14 per N-513-4 on January 8, 2018;

(2) Schedule changes required due to grid cold weather alert and emergent direct current (DC) ground troubleshooting on January 18, 2018;

(3) 2A emergency diesel generator maintenance outage on January 29, 2018; and

(4) Schedule changes required due to unplanned extension of 2A residual heat removal pump work window on March 15, 2018.

71111.15Operability Determinations and Functionality Assessments

The inspectors evaluated the following operability determinations and functionality assessments:

(1) Action Request (AR) 04097787, Unexpected AlarmIonization High 1VD01JB for 1B diesel generator ventilation dampers 1VD20Y and 1VD21Y when they failed to close as expected on January 27, 2018;

(2) AR 04098736, NRC Design Bases Assurance Inspection (DBAI) - In-Service Testing (IST) Non-Compliance Issue, on January 30, 2018, for containment floor drain isolation valves during the DBAI when inspectors identified that control air check valves had never been tested with loss of air pressure since installation;

(3) AR 04099325, 1SX01PB Oil Leak On Shaft Driven Pump, on January 31, 2018, for the 1B SX pump with an oil leak from the seal of the shaft driven oil pump;

(4) AR 04103905, NRC DBAIFault On Nonsafety-Related Loads Supplied by Instrument Inverter, identified on February 7, 2018, during the DBAI when inspectors raised questions about the impact on the inverter when nonsafety-related loads failed;

(5) AR 04103905, 1SI8812B Will Not Go Full Open, on February 15, 2018, after the valve stopped stroking open at 50 percent of full travel and operators manually positioned the valve using the valve handwheel;

(6) AR 04115769, 2B Containment Spray (CS) Pump Cubicle Cooler Flow Less Than Surveillance Requirement on March 27, 2018; and

(7) AR 04117744, 1B DG Fuel Oil Transfer Pump, 1DO01PB, Low Flow on March 28, 2018.

The inspectors also reviewed the status of URI 05000454/2016001-01, and 05000455/2016001-01. This did not constitute an inspection sample.

71111.18Plant Modifications

The inspectors evaluated the following temporary or permanent modifications:

(1) Engineering Change (EC) 0402668 which removed the actuator and blocked open the offgas system vent stack isolation valve so that it remained open at all times.

71111.19Post Maintenance Testing

The inspectors evaluated the following post maintenance tests:

(1) Work Order (WO) 04722857, Emergency Diesel Generator Lube Oil Lower Cooler Minor Leak on February 2, 2018;

(2) WO 01941343, Replace Fuel Oil Ratio Relay 2PY-DG8035A on February 15, 2018;

(3) WO 04737408, Essential Service Water Makeup Pump 0B Monthly Operability Surveillance following 0B pump work window on February 16, 2018; and

(4) WO 04724172, Comprehensive Inservice Testing (IST) Requirements for Containment Spray Pump 1CS01PA following the 1A containment spray pump work window.

71111.22Surveillance Testing The inspectors evaluated the following surveillance tests: Routine

(1) 2BOSR SX-SA1, Diesel Generator Essential Service Water Crosstie Line Semi-annual Flush, Revision 21, on February 27, 2018; and

(2) 1BOSR 3.1.5-2, Train B Solid State Protection System Surveillance, Revision 42, on

===March 20, 2018.

In-service (3 Samples)===

(1) 2BOSR 5.5.8.RH.5-2A, Group A Inservice Testing (IST) Requirements For Residual Heat Removal Pump 2RH01PB, Revision 9, on January 24, 2018;

(2) 2BOSR 5.5.8.CC.5-1C, Comprehensive Inservice Testing (IST) Surveillance Requirements For Component Cooling Pump 2CC01PA, Revision 7, on February 6, 2018; and

(3) 1BOSR 5.5.8.AF.5-1b, Group B Inservice Testing (IST) Requirements for Motor Driven Auxiliary Feedwater Pump 1AF01PA, Revision 10, on March 15, 2018.

71114.06Drill Evaluation Emergency Planning Drill

The inspectors evaluated an emergency drill with the Technical Support Center and the Operations Support Center participating on January 31, 2018.

The inspectors evaluated an emergency drill with the Main Control Room (Simulator),

Technical Support Center and the Operations Support Center participating on March 21,

RADIATION SAFETY

71124.05Radiation Monitoring Instrumentation Walk Downs and Observations

The inspectors evaluated radiation monitoring instrumentation during plant walkdowns.

Calibration and Testing Program (1 Sample)

The inspectors evaluated the licensees calibration and testing program.

OTHER ACTIVITIES - BASELINE

71151Performance Indicator Verification

The inspectors verified the licensee performance indicators submittals listed below:

(1) IE01: Unplanned Scrams Per 7000 Critical Hours-2 Samples (01/01/2017-12/31/2017);

(2) IE03: Unplanned Power Changes Per 7000 Critical Hours-2 Samples (01/01/2017-12/31/2017); and

(3) IE04: Unplanned Scrams with Complications-2 Samples (01/01/2017-12/31/2017).

71152Problem Identification and Resolution Annual Follow-Up of Selected Issues

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

(1) AR 01488097, Untimely Corrective ActionActive Valve List Discrepancies, initiated on March 12, 2013. This issue was NRC-identified during a corrective action review in 2015, but was determined to be a violation of not more than minor significance and was documented in Inspection Report 05000454/2015003, 05000455/2015003.

Licensee investigation into the nonconforming condition identified additional corrective actions and the final actions were completed on December 13, 2017; and

(2) AR 04106648, Component Cooling Water (CC) System Does Not Comply With General Design Criteria (GDC) 44, initiated on February 21,

OTHER ACTIVITIES

TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL 60855.1Operation of an Independent Spent Fuel Storage Installation at Operating Plants The inspectors evaluated the licensees operation of the independent spent fuel storage installation (ISFSI) from March 26 to March 30, 2018. Specifically, the inspectors evaluated:

(1) a heavy lift of the loaded transfer cask (HI-TRAC) from the wet pit to the dry pit;

(2) welding of the root pass of the Multi-Purpose Canister (MPC) lid-to-shell weld;

(3) processing of the MPC, including removal of bulk water and drying and backfill with helium;

(4) visual and dye penetrant examination of the vent and drain port welds and performance of a helium leak test;

(5) the condition of the ISFSI pad, loaded storage casks, and heavy haul path by performing a walkdown;

(6) the radiological conditions on the ISFSI pad by performing surveys and verifying compliance with 72.104 and the dose limit for any real individual;

(7) selection of spent fuel for loading in accordance with the Certificate of Compliance (CoC); and

(8) changes to the 72.212 report and the plant Emergency Plan into which the ISFSI is incorporated, and selected 72.48 screenings performed sionce the previous ISFSI inspection.

INSPECTION RESULTS

No findings or violations were identified.

71111.15Operability Determinations and Functionality Assessments Unresolved Item Failure to Enter Technical Specification Limiting Condition 71111.15 (Closed) for Operation Action Requirement with Auxiliary Feedwater Flow Control Valves Failed Open 05000454/2016001-01, 05000455/2016001-01

Description:

As discussed in Inspection Report 05000454/2016001, 05000455/2016001, the inspectors were concerned that when all air is isolated to the auxiliary feedwater flow control valve actuators, operators may not be able to throttle or isolate flow to a ruptured steam generator quickly enough to prevent overfill of the steam generator, assuming the motor-operated containment isolation valve fails to close, which could challenge the integrity of containment.

As such, the inspectors were concerned that the licensee failed to enter a TS LCO action requirement when the air to the actuator was isolated. To determine whether a performance deficiency or violation existed, the inspectors needed to determine whether a TS LCO should have been established for the ability of the AF005 valves to close to mitigate a steam generator tube rupture event, and whether the licensees modifications and license amendment requests properly addressed the establishment of an LCO for this function of the structure, system, or component (SSC).

Corrective Action References:

(1) AR 2607148; Procedure Discrepancy on Failing Instrument Air to AF005 Valves;

(2) AR 2661562; URI: TS Limiting Condition of Operations (LCO) for AF Flow Control Valves Failed Open.

Closure Basis: Title 10 CFR 50.26(c)(2)(ii)(C) requires that a TS LCO must be established for each SSC that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that assumes the failure of, or presents a challenge to, the integrity of a fission product barrier. The inspectors reviewed the policy statements associated with 10 CFR 50.26(c)(2)(ii)(C) and concluded that a TS LCO was not required for these flow control valves since they were not part of the primary success path. Therefore, no violation of NRC regulations was identified.

This URI is closed.

EXIT MEETINGS AND DEBRIEFS

The inspectors confirmed that proprietary information was controlled to protect it from public disclosure. No proprietary information was documented in this report.

• On February 2, 2018, the inspectors presented the radiation protection inspection results to Mr. P. Boyle, Work Management Director, and other members of the licensee staff.

• On March 30, 2018, the inspectors presented the independent spent fuel storage installation inspection results to Mr. M. Kanavos, Site Vice President, and other members of the licensee staff.

• On April 18, 2018, the inspectors presented the quarterly integrated inspection results to Mr. M. Kanavos, Site Vice President, and other members of the licensee staff.

DOCUMENTS REVIEWED

71111.01Adverse Weather Protection

- UFSAR Revision 16, Section 3.4 Water Level (Flood) Design

- 0BOA ENV-1, Adverse Weather Conditions, Unit 0, Revision 124

- 1BOA ENV-1, Adverse Weather Conditions, Unit 1, Revision 101

- 2BOA ENV-1, Adverse Weather Conditions, Unit 2, Revision 101

- 0BOA ENV-2, Rock River Abnormal Water Level, Unit 0, Revision 103

71111.04Equipment Alignment

- Drawing M-124, Sheet 3; Diagram of Condensate Piping, Revision AR

- Drawing M-145, Sheet 1; Diagram of Condensate Booster Piping, Revision X

- Drawing M-42, Sheet 1A; Diagram of Essential Service Water, Revision AR

- Drawing M-42, Sheet 1B; Diagram of Essential Service Water, Revision AT

- Drawing M-130, Sheet 1A; Diagram of Diesel Oil and Fuel Oil Supply, Revision BH

- Drawing M-130, Sheet 1B; Diagram of Diesel Oil and Fuel Oil Supply, Revision BE

- Drawing M-152, Sheet 9; Diagram of Diesel Generator Lube Oil Schematic, Revision

- BOP DG-M2B, TRAIN B Diesel Generator System Valve Lineup, Revision 8

- BOP DG-E2, Diesel Generator Electrical Lineup Unit 2 DG, Revision 6

- AR 04098118, 2B DG Crankcase Oil Level Low

- 2BOSR 8.4.2-2, Unit 2 Bus 212 125V Battery Charger Operability, Revision 1

71111.05QFire Protection Quarterly

- Pre-Fire Plan FZ 5.4-2, Division 22 Miscellaneous Electrical Equipment and Battery Room,

Revision 2

- Pre-Fire Plan #197, FZ 18.3-1, Unit 1 Main Steam and Auxiliary Feedwater Pipe Tunnel,

Revision 2

- Pre-Fire Plan FZ 10.1-1, 1B Diesel Fuel Oil Storage Tank; Revision 2

- Pre-Fire Plan FZ 8.6-0, Turbine Building Northwest End, Revision 2

- Pre-Fire Plan FZ 8.6-0, Turbine Building Northwest Center, Revision 2

- Pre-Fire Plan FZ 8.6-0, Turbine Building Southwest Center, Revision 1

- Pre-Fire Plan FZ 8.6-0, Turbine Building Southwest End, Revision 2

- Pre-Fire Plan FZ 8.6-0, Turbine Building Southeast End, Revision 1

- Pre-Fire Plan FZ 8.6-0, Turbine Building Southeast Center, Revision 3

- Pre-Fire Plan FZ 8.6-0, Turbine Building Northeast End, Revision 2

- Pre-Fire Plan FZ 8.6-0, Turbine Building Northeast End, Revision 1

- Pre-Fire Plan FZ 8.5-1, Turbine Building 426 Elevation, Unit 1 General Area - Northeast,

Revision 1

- Pre-Fire Plan FZ 8.5-1, Turbine Building 426 Elevation, Unit 1 General Area - Northwest,

Revision 1

- Pre-Fire Plan FZ 8.5-1, Turbine Building 426 Elevation, Unit 1 General Area - Southwest,

Revision 1

- Pre-Fire Plan FZ 8.5-1, Turbine Building 426 Elevation, Unit 1 General Area - Southeast,

Revision 1

- Pre-Fire Plan FZ 8.5-2, Turbine Building 426 Elevation, Unit 2 General Area - Northeast,

Revision 2

- Pre-Fire Plan FZ 8.5-2, Turbine Building 426 Elevation, Unit 2 General Area - Northwest,

Revision 2

- Pre-Fire Plan FZ 8.5-2, Turbine Building 426 Elevation, Unit 2 General Area - Southeast,

Revision 2

- Pre-Fire Plan FZ 8.5-2, Turbine Building 426 Elevation, Unit 2 General Area - Southwest,

Revision 2

71111.06Flood Protection Measures

- UFSAR Section 2.4, Water Level (Flood) Design

- 0BOA ENV-2, Rock River Abnormal Water Level, Unit 0; Revision 103

71111.07Heat Sink Performance

- AR 04098363, 2A DG Upper Jacket Water Channel Head Coating Degradation

- AR 04098444, Degraded Bolting

- AR 04098454; Degraded Bolting

- AR 04098893, Eddy Current Results of 2A DG Jacket Water Lower Cooler

- AR 04099360, Victaulic Couplings Replacement PM Needs to Be Rescheduled

- AR 04099457, 2A DG Jacket Water Leaks at Couplings in Pipes to Turbo

71111.12Maintenance Effectiveness

- Maintenance Rule System Basis Document for Function SI-07

- Maintenance Rule System Basis Document for Function DC-02

- WO 4698697; 212 Battery Charger Input Breaker Tripped During 2BOSR 8.1.11-2

- Power Labs Failure Analysis Report BYR-65147 dated 01/30/2018; Failure Analysis of a

Sensing & Current Limit Board from Byron Station

71111.13Maintenance Risk Assessments and Emergent Work Control

- EC 622466, Functionality Evaluation For Through Wall Leak On 0FC03B-14 per N-513-4

- WC-AA-104, Integrated Risk Management, Revision 25

- AD-AA-3000, Nuclear Risk Management Process, Revision 2

71111.15Operability Determinations and Functionality Assessments

- EC 339734, Evaluation of Past Operability of 2B SX Pump with 30 drops/minute Oil Leak,

Revision 000

- TS 3.7.8, Essential Service Water (SX) System and Associated Bases

- WO 01733606, MOV PM Actuator inspection, Diagnostic Testing, Closed 10/15/2015

- TS 3.5.2, Emergency Core Cooling Systems - Operating and Associated Bases

- 1BOSR 0.5-2.SI.1-2, Unit One 1SI8821B, 1SI8812B, 1SI8804B, 1SI8920B, Exercise Test,

Revision 11

- WO 04747012, 1SI8812B Will Not Go Full Open, Closed 02/20/2018

- AR 04088691, 1B DOST Room Ionization Detector False Alarm

- BAR 1VD01JB-1-A7, Diesel Oil Storage Room 1B Ionization High

- AR 04098736, NRC DBAI - IST Non-Compliance Issue

- BB-SURV-013, Risk Assessment Missed Surveillance - Tech Spec Surveillance

Requirement 3.6.3.8, IR 4096766, Revision 0

- TS 3.6.3, Containment Isolation Valves and Associated Bases

- BYR10-012, Air to Water Cubicle Cooler Heat Exchanger Tube Plugging, Revision 004

- 2BOSR 6.6.2-1, Unit 2 Reactor Containment Fan Cooler Surveillance, Revision 35

- 1BOSR 5.5.8.DO-1, Test of the Diesel Oil Transfer System, Revision 3

- M-50, Diagram of Diesel Fuel Oil, Sheets 1A and 1B

71111.18Plant Modifications

- EC 402668, Install Valve Block On 2OG035, Revision 000

- Calculation BYR16-012, Off Gas Filter Analysis, Revision 000

- EC 402667, Install Valve Block on 1OG035 To Eliminate a Unit Single Point Vulnerability,

Revision 2

- NRC Regulatory Guide 1.109, Calculation of Annual Doses To Man - From Routine Releases

of Reactor Effluents for the Purpose of Evaluating Compliance With 10 CFR Part 50,

Appendix I, Revision 1

- NRC NUREG-0017, Calculation of Releases of Radioactive Materials in Gaseous and Liquid

Effluents From Pressurized Water Reactors (PWR-GALE Code), April 1976

- TS 5.5.4, Radioactive Effluent Controls Program

- UFSAR Section 11.2, Liquid Waste Management Systems

- UFSAR Section 11.3, Gaseous Waste Management Systems

71111.19Post Maintenance Testing

- AR 04104698, 0B SX Makeup Pump Failed To Auto-Start Following Maintenance

- AR 04056789, 0B SM Makeup Pump Tripped During Run, No Alarms Received

- AR 04107385, Critique For 0B SX Makeup Pump LCO - 2/12 Week

- AR 04104414, NRC Identified Quality Review Appropriate

- AR 04104463, Work Order Instructions For PMT Not Documenting Actual Work

- AR 04099911, Fit Between Sheet and Shell is Not Concentric

- AR 04115101, 1CS004A Difficult to Close

71111.22Surveillance Testing

- WO 04703871, 2BOSR 5.5.8.RH.5-2A - 2B RH Group A Test

- WO 04713587, 2BOSR 5.5.8.CC.5 -1C 2A CC Comprehensive

- AR 04108976, Low Flows During 1BOSR SX-SA1 and 1BOSR SX-SA2

- AR 04117185, 1PI-AF054 As Found Value Greater Than 1.5 Times Tolerance

71114.06Drill Evaluation

- Drill Scenario for 01/31/2018

71124.05Radiation Monitoring Instrumentation

- Self-Assessment Exelon Powerlabs; February 28, 2017

- Implementation of Weekly Source Checks for RCA/PA Exit Monitors; June 3, 2016

- RP-AA-700; Controls for RP Instrumentation; Revision 4

- RP-AA-700-1208; Operation of Shepherd Model 89 Calibrator; Revision 35557

- Calibration; Ludlum Model 177 Serial Number 3155557; January 12, 2018

- Calibration; Eberline Model RM-14 Serial Number 3221; January 23, 2018

- Calibration; MG Telepole; Serial Number 0010635; January 23, 2018

- Calibration; Bicron Model RSO-5; Serial Number B581N; January 22, 2018

- Calibration; Eberline Model RO20AA Serial Number 12544; January 22, 2018

- Calibration; MGP Ram Gam Serial Number 079362; January 4, 2018

- Calibration; Eberline AMS-4 Serial Number 13016/12586; January 4, 2018

- Calibration; Thermo Scientific Microrem Serial Number 19189; November 7, 2017

- Calibration; Ludlum Model 9-7 Serial Number 26469; September 26, 2017

- Calibration; Ludlum Model 3030P Serial Number 322993; November 28, 2017

- Calibration; Radeco Model HD28/A Serial Number 2522; September 26, 2017

- Calibration; PM-12 Serial Number 38; December 22, 2017

- Calibration; Argos Serial Number 140; December 21, 2017

- Certification JL Shepherd Model 89; September 26, 2017

- Calibration; Fastscan WBC #1; September 28, 2017

- Calibration; Electronic Dosimeters; Various Records

- Calibration; Gamma Spectroscopy Systems; Various Records

- AR 03971351; LLDs Not Performed on HPGEs per CY-AA-130-201; February 7, 2017

- AR 04025045; Accuscan II Will Not Maintain High Voltage; June 23, 2017

- AR 04026466; EP Field Response Team Vans After Use Inventory Discrepancy,

June 28, 2017

- AR 04086137; ERO Air Samplers Found Out of Tolerance During Calibration; December 20,

2017

71151Performance Indicator Verification

- NEI 99-02, Revision 7; Regulatory Assessment Performance Indicator Guideline

- Exelon Nuclear Performance Summary; Byron P.2: Power History Curves

71152Problem Identification and Resolution

- UFSAR Revision 16, Section 3.1.2.4.15 Evaluation Against Criterion 44 - Cooling Water

- EC 360252, Review of IST and UFSAR Table Active Valve List, Revision 000

- UFSAR Change 16-034, Revision of UFSAR Table 3.9-16 to Revise the Active Valve List for

Byron Station, Dated 07/20/2015

- AR 01303927, Component Cooling Documentation for Compliance With GDC 5; Initiated

2/16/2011

- AR 04106723, Unanalyzed CC Flow Path May Impact CC to RH HX; initiated 02/21/2018

60855.1Operation of an Independent Spent Fuel Storage Installation at Operating Plants

- 0BDCSR 3.3.1.1; DCS Boron Concentration; Revision 6

- Selected ISFSI-Related Action Requests from 2015 to 2018

- Selected 72.48 Screenings from 2015 to 2018

- Selected Dry Cask Personnel Qualifications

- AR 02545794; PCI Welder Not Qualified for DCS Remote Welding Activities; 08/24/2015

- AR 02727391; NOSA-BYR-16-11 Byron ISFSI Audit; 10/12/2016

- AR 04120630; DCS Stack-Up and Download Schedule Delay; 03/29/2018

- ASME - Welder Maintenance Logs

- ASME Section IX - Welder Performance Qualifications

- BFP FH-20; Operation of Fuel Handling Building Crane; Revision 34

- BFP FH-22; Rigging Equipment Inspection; Revision 4

- BFP FH-62; HI-STORM/MPC Delivery Inspection; Revision 1

- BFP FH-63; HI-STORM Inspection; Revision 5

- BFP FH-65; Spent Fuel Cask Site Transportation; Revision 21

- BFP FH-68; HI-TRAC Preparation; Revision 10

- BFP FH-69; HI-TRAC Movement Within the Fuel Building; Revision 28

- BFP FH-70; HI-TRAC Loading Operations; Revision 25

- BFP FH-75; MPC Inspection; Revision 9

- BFP FH-81; DCS Campaign Preparations; Revision 10a

- BFP FH-82; MPC Unloading Operations; Revision 5

- BFP FH-83; Spent Fuel Cask Contingency Actions; Revision 8

- BFP FH-85; Dry Cask Storage Special Lifting Device Annual Testing; Revision 5

- BFP FH-86; DCS/ISFSI Inspection Surveillance Program; Revision 2

- BFP FH-87; Transporter Preventative Maintenance; Revision 3

- BYR08-127; Byron 1 Cycles 1 to 14 and Byron 2 Cycles 1 to 13 Cask Loader Database

Population; Revision 0

- BYR17-056; Fuel Selection Packages BYR-0031 Thru BYR-0035 for Byron 2018

Campaign - ISFSI; Revision 0

- BYR17-057; Alternate Fuel Assembly List for Byron 2018 ISFSI Campaign - ISFSI; Revision 0

- Byron Nuclear Generating Station Units 1 and 2: Annual Radiological Environmental

Operating Report: 1 January Through 31 December 2015; May 2016

- Byron Nuclear Generating Station Units 1 and 2: Annual Radiological Environmental

Operating Report: 1 January Through 31 December 2016; April 2017

- Byron Nuclear Power Station Units 1 and 2 10 CFR 72.212 Evaluation Report

Docket 72-0068; Revision 5

- Byron Special Interest TLDs; Quarterly Data from 2009 through 2017

- Drawing 3923, Sheet 3; MPC Enclosure: Enclosure Vessel: Elevation Details; Revision 29

through 35

- Drawing 4838, Sheet 4; MPC-24, 32, & 68 Lid Details; Revision 23, 25, and 34

- EP-AA-1002, Addendum 3; Emergency Action Levels for Byron Station; Revision 1 and 2

- GQP-9.2; High Temperature Liquid Penetrant Examination and Acceptance Standards for

Welds, Base Materials and Cladding (50°F - 350°F); Revision 10

- GQP-9.6; Visual Examination of Welds; Revision 18

- H2-MON-002; Hydrogen Monitoring for Holtec Canisters; Revision 10

- MA-AA-716-021; Rigging and Lifting Program; Revision 28

- NDE Personnel Certifications

- NF-AA-622; Fuel Selection and Documentation for Dry Cask Loading; Revision 4

- NO-AA-10; Exelon Generation Company, LLC: Quality Assurance Topical Report (QATR);

Revision 92

- NOSA-BYR-16-11; Independent Spent Fuel Storage Installation Audit Report (AR 2727391);

Revision 1

- OU-AA-630; Dry Cask Program Implementation; Revision 9

- OU-AA-630-1000; Spent Fuel Loading Campaign Management; Revision 8

- OU-AA-630-1002; Guidance for Holtec HI-STORMs and MPCs Delivery/Fit-

Up/Dimensional/Pre-Use Inspections; Revision 0

- OU-MW-671-300; MPC Processing: Forced Helium Dehydration (FHD) for PWRs; Revision 7

- OU-MW-671-300, Step 4.2.25; MPC Surface Contamination Verification Technical

Specification Survey; 03/12/2018

- OU-MW-671-300, Step 4.2.25; MPC Surface Contamination Verification Technical

Specification Survey; 03/26/2018

- OU-MW-671-300, Step 4.12.2; MPC Surface Contamination Verification Technical

Specification Survey; 03/15/2018

- PI-AA-126-1001-F-01; Byron Spent Fuel Loading Campaign (SFLC) Readiness Assessment;

01/18/2018

- PI-CNSTR-OP-EXE-H-01; Closure Welding of Holtec Multi-Purpose Canisters at Exelon

Facilities; Revision 18

- Procedure #36272-10; Exelon Byron and Braidwood Fuel Handling Building Single Failure

Proof Trolley: Factory Acceptance Test Procedure; 01/23/2009

- RP-AA-3041; Holtec HI-TRAC Radiation Survey; Revision 0

- RP-AA-3041, Attachment 1; Byron HI-TRAC Radiation Survey (MPC SN 0362); 03/12/2018

- RP-AA-3041, Attachment 1; Byron HI-TRAC Radiation Survey (MPC SN 0362); 03/15/2018

- RP-AA-3041, Attachment 1; Byron HI-TRAC Radiation Survey (MPC SN 0410); 03/26/2018

- RP-AA-3042; Holtec HI-STORM Radiation Survey; Revision 0

- RP-AA-3042, Attachment 2; Byron Hi-STORM Radiation Survey (HI-STORM SN 0362);

03/19/2018

- RP-AA-3043, Attachment 1; ISFSI Radiation Survey Braidwood & Byron; 03/19/2018

- RP-AA-376; Radiological Postings, Labeling, and Markings; Revision 9

- RP-AA-376-1001; Radiological Posting, Labeling and Marking Standard; Revision 14

- RP-AA-401; Dry Cask Storage ALARA Plan; 02/06/2018

- RP-AA-401-1006; Controls for Independent Spent Fuel Storage (ISFSI) Associated Activities;

Revision 0

- RP-AA-410; Selection, Use, and Control of Protective Clothing; Revision 8

- TWE-DCS-BYR-001; Exelon Independent Review of Byron Generating Station Unit 1

Cycles 1 - 14 and Unit 2 Cycles 1 - 13 Fuel Failure Assessment: Prepared by TransWare

Enterprises; Revision 0

- WO 01098478-24; CAM Perform Station Acceptance Testing per EC 367121; 04/30/2009

- WO 01893481-01; RXS Inspect MPC Spider Lift; 11/13/2017

- WO 01932883-01; RXS HI STORM Lift Bracket Inspection - 0FI907A & 0FI907B; 06/09/2017

- WO 01933307-01; RXS HI-TRACK Lift Trunnion Inspection; 10/25/2017

- WO 01942861-01; RXS Lift Yoke Inspection and NDE; 11/16/2017

- WO 01946588-01; RXS MPC Lift Cleat Inspection; 11/13/2017

- WO 04587600-01; EWP LR - MM Perform MM Annual Surveillance for 0HC03G; 01/11/2018

- WO 04588964-01; EWP EM Crane Inspection (Fuel Handling Bldg) - 0HC03G; 01/05/2018

- WO 04746835-01; EWP MM Perform Surveillance 0HC03G Monthly Inspection; 03/07/2018

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION III

2443 WARRENVILLE RD. SUITE 210

LISLE, ILLINOIS 60532-4352

May 7, 2018

Mr. Bryan C. Hanson

Senior VP, Exelon Generation Company, LLC

President and CNO, Exelon Nuclear

4300 Winfield Road

Warrenville, IL 60555

SUBJECT: BYRON STATION, UNITS 1 AND 2NRC INTEGRATED INSPECTION

REPORT 05000454/2018001; 05000455/2018001 and ISFSI CASK LOADING

INSPECTION REPORT 07200068/2018001

Dear Mr. Hanson:

On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed a quarterly

integrated inspection at your Byron Station, Units 1 and 2. On April 18, 2018, the NRC

inspectors discussed the results of this inspection with Mr. M. Kanavos and other members of

your staff. The results of this inspection are documented in the enclosed report.

The NRC did not identify any findings of significance during this inspection period.

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 10 CFR 2.390, Public Inspections, Exemptions, Requests for

Withholding.

Sincerely,

/RA/

Eric Duncan, Chief

Branch 3

Division of Reactor Projects

Docket Nos. 50-454; 50-455; 72-68

License Nos. NPF-37; NPF-66

Enclosure:

IR 05000454/2018001; 05000455/2018001;

20068/2018001

cc: Distribution via LISTSERV

B. Hanson -2-

Letter to

B. Hanson from E. Duncan dated May 7, 2018

SUBJECT: BYRON STATION, UNITS 1 AND 2NRC INTEGRATED INSPECTION

REPORT 05000454/2018001; 05000455/2018001 and ISFSI CASK LOADING

INSPECTION REPORT 07200068/2018001