IR 05000454/2020011

Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000454/2020011 and 05000455/2020011

ML20273A303
Person / Time
Site:	Byron
Issue date:	09/29/2020
From:	Richard Skokowski Engineering Branch 3
To:	Bryan Hanson Exelon Generation Co, Exelon Nuclear
References
IR 2020011
Download: ML20273A303 (8)

Text

September 29, 2020

SUBJECT:

BYRON STATION - TRIENNIAL INSPECTION OF EVALUATION OF CHANGES, TESTS AND EXPERIMENTS BASELINE INSPECTION REPORT 05000454/2020011 AND 05000455/2020011

Dear Mr. Hanson:

On September 9, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Byron Station and discussed the results of this inspection with Mr. H. Welt, Acting Plant Manager 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/

Richard A. Skokowski, Chief Engineering Branch 3 Division of Reactor Safety 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: 05000454/2020011 and 05000455/2020011 Enterprise Identifier: I-2020-011-0044 Licensee: Exelon Generation Company, LLC Facility: Byron Station Location: Byron, IL Inspection Dates: August 31, 2020 to September 09, 2020 Inspectors: J. Bozga, Senior Reactor Inspector M. Holmberg, Senior Reactor Inspector A. Shaikh, Senior Reactor Inspector Approved By: Richard A. Skokowski, Chief Engineering Branch 3 Division of Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial inspection of evaluation of changes, tests and experiments baseline 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.

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), regional inspectors were directed to begin telework. For the inspection documented below, it was determined that the objectives and requirements stated in the IP could be performed remotely.

REACTOR SAFETY

71111.17T - Evaluations of Changes, Tests, and Experiments Sample Selection (IP Section 02.01)

The inspectors reviewed the following evaluations, screenings, and/or applicability determinations for 10 CFR 50.59 from August 31, 2020 to September 09, 2020.

(1) 50.59 Evaluation 6G-20-001, Lost Parts Evaluation for 2B Charging Pump Mechanical Seal Debris, Revision 0

(2) 50.59 Evaluation 6G-17-004, Temporary Configuration Change Package to Install Pneumatic Jumper to Open 1WG-074, Revision 0

(3) 50.59 Screening 6E-17-034, Scaling Changes to Rod Insertion Limits Alarm Instrumentation to Reflect Byron Unit 2 Cycle 21 Changes to Rod Insertion Limits Figure and Rod Control Cluster Assembly Park Position, Revision 0

(4) 50.59 Screening 6E-17-036, Revise Process Computer Rod Supervision Constants to Reflect Byron Unit 2 Cycle 21 Change to Rod Control Cluster Assembly Fully Withdrawn Park Position from 231 Steps to 228 Steps, Revision 0

(5) 50.59 Screening 6E-17-063, UFSAR Update to Reflect 17 x 17 OFA Top Grid Bulge Connection Design Change, Revision 0

(6) 50.59 Screening 6E-18-013, Install 2A Safety Injection Vent Path and Isolation Valve, Revision 0

(7) 50.59 Screening 6E-18-036, Byron Unit 1 Cycle 23 Core Reload and Operation, Revision 1

(8) 50.59 Screening 6E-18-062, Add the Maximum Post Loss of Coolant Accident Component Cooling System Supply Water Temperature to the Updated Final Safety Analysis Report and Bases for Technical Specification 3.7.7, Revision 0

(9) 50.59 Screening 6E-20-007, Byron Unit 1 Cycle 24 Core Reload, Revision 0

(10) 50.59 Screening 6E-18-012, Revise UFSAR Section 15.6.2.2 to Correct CVCS Line Break Location Description, Revision 0

(11) 50.59 Screening 6E-18-046, SAT 242-2 FP Deluge and Thermistor Wire Mod Unit 2, Revision 0

(12) 50.59 Screening 6E-18-027, Revise Setpoint of OPDS-VS022 to Prevent Spurious High-Differential Pressure Trip and Alarm of Service Building Supply Fan 0VS01C, Revision 0

(13) 50.59 Screening 6E-18-028, Revising AST Accident Dose Calculations, Revision 0

(14) 50.59 Screening 6E-20-004, Lifting AR-VD62X Trip Contact for DG Room 1B Supply Fan 1VD01CB, Revision 0

(15) 50.59 Screening 6E-17-082, Change the Normal Position of the Breakers for MOVs 1(2) CC9415 from On to Off, Revision 0

(16) 50.59 Screening 6E-17-001, Install 1(2) CV8351 as a Redundant Isolation Valve to 1(2) CV8350, Revision 0

(17) 50.59 Screening 6E-17-010, Permanent Installation of 125 Amp HFD in 150 HFB Application for MCC035-2 Compartment B1-B, Revision 0

(18) 50.59 Evaluation 6G-17-005, Provide Capability to Disable Water Hammer Prevention System (WHPS) Feedwater (FW) Isolation Signals during Normal Power Operation &

Change WHPS SG Low Pressure/Level Control Relay Operation from Actuate on De-Energized to Actuate on Energized, Revision 0

(19) 50.59 Screening 6E-17-070, Lead Shielding on Valve 2CV8527B and Pipe Around It, Revision 0

(20) 50.59 Screening 6E-17-079, Lead Shielding on Valve 2CV8527B and Pipe Around It, Revision 1

(21) 50.59 Screening 6E-17-080, Applications of Higher Allowable Stresses for ASME and Non-Nuclear Piping, Revision 0

(22) 50.59 Screening 6E-18-065, Long-Term Lead Shielding Evaluation per T-18-02 Shielding Request U/1 CV Valve Aisle, Revision 0

(23) 50.59 Screening 6E-19-005, Reclassify ASME III FP Piping/Valves/Components in Seismically Qualified Areas, Revision 0

(24) 50.59 Screening 6E-19-007, Revise UFSAR Section 3.6.1.3.1 Description for Byron to Reference Section 3.11.10.1 and Improve Clarity, Revision 0

(25) 50.59 Screening 6E-19-024, Expand HELB Sensor Network into Area 5 for Coverage of SG Blowdown HELC, Revision 0

(26) 50.59 Screening 6E-19-029, Long-Term Lead Shielding Evaluation U/2 Valve Aisle (Shielding Requests T-19-02, 03, 04), Revision 0

(27) 50.59 Screening 6E-19-035, Revise TRM 3.7.b Snubbers, Revision 0

(28) 50.59 Screening 6E-19-044, Temporary Scaffold FNE 1105 (more than 90 days) for 2FW009C Valve, Revision 0

(29) 50.59 Evaluation 6G-19-001, Reclassify ASME III FP Piping/Valves/Components in Seismically Qualified Areas, Revision 0

(30) 50.59 Screening 6E-20-008, Expand HELB Sensor Network into Area 7 (unit 2) for Coverage of SG Blowdown HELC, Revision

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On September 9, 2020, the inspectors presented the triennial inspection of evaluation of changes, tests and experiments baseline inspection results to Mr. H. Welt, Acting Plant Manager and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.17T Calculations BYR12-121 Seismic Qualification of SOR Temperature Switches 0B

BYR12-121 Seismic Qualification of SOR Temperature Switches 0A

BYR99-125 Rod Insertion Limit (RIL) Alarm and Indication Loop (2RC- 5

0412-A) Scaling Calculation

Corrective Action 4044330 Problem with 50.59 Resource Manual 08/22/2017

Documents 4366097 2020 NRC 50.59 Inspection: Cannot Locate 50.59 Screening 08/28/2020

Corrective Action 4367096 UFSAR Change DRP-18-023 Needs Revision 09/02/2020

Documents

Resulting from

Inspection

Engineering 381903 Install 2A Safety Injection Vent Path and Isolation Valve 2

Changes 406564 Install 1(2) CV8351 as a Redundant Isolation Valve to 1(2) 0

CV8350

406640 Revise U-2 Rod Insertion Limit (RIL) Instrument Scaling Due 0

to Control Rod Full Out Park Position Change from 231

Steps to 228 Byron Unit 2 Cycle 21 Operation after B2R20

406641 Revise Process Computer Rod Supervision Constants (Unit 0

2) Due to Change in RCCA Park Position from 231 to 228

Steps for B2C21

617310 17X17 OFA Fuel Top Grid Bulge Connection Design Change 0

Byron 1 and 2

617922 Permanent Installation of 125 Amp HFD in 150 Amp HFB 0

Application for MCC 035-2 Compartment B1-B (0AP93E-

B1B)

619975 TCCP to Install Pneumatic Jumper to Open 1WG074 0

21662 Lead Shielding on Valve 2CV8527B and Pipe Around It 0

2005 Byron Unit 1 Cycle 23 Core Reload Design 0

2269 Change the Normal Position of the Breakers for MOVs 1(2) 0

CC 9415 from "On" to "Off"

2345 ASME Code Reconciliation for Revised Material Allowables 0

2684 Process Revised AST Calculations BYR04-051/BRW04- 0

0038-M, Due to RATRAD Error #17 and Daughtering Effect

Inspection Type Designation Description or Title Revision or

Procedure Date

24075 Revise Setpoint of OPDS-VS022 to Prevent Spurious High 0

Differential Pressure Trip and Alarm of Service Building

Supply Fan 0VS01C

25276 SAT 242-2 FP Deluge and Thermistor Wire MOD Unit 2 0

26369 Long-Term Lead Shielding Evaluation per T-18-02 Shielding 0

Request U/1 CV Valve Aisle

26662 Reclassify ASME III FP Piping/Valves/Components in 0

Seismically

26968 Expand Helb Sensor Network into Area 5 for Coverage of SG 0

Blowdown Helc

26969 Expand Helb Sensor Network into Area 7 (Unit 2) for 0

Coverage of SG Blowdown Helc

28650 Long-Term Lead Shielding Evaluation U/2 Valve Aisle 0

(Shielding Requests T-19-02, -03, -04)

630419 Lifting AR-VD62X Trip Contact for DG Room 1B Supply Fan 0

1VD01CB

630528 Lost Parts Evaluation 2B CV Pump Mechanical Seal Debris 1

Engineering 617266 Provide Capability to Disable Water Hammer Prevention 2

Evaluations System (WHPS) Feedwater (FW) Isolation Signals During

Normal Power Operation & Change WHPS SG Low

Pressure/Level Control Relay Operation from Actuate on De-

Energized to Actuate on Energized

NF194911 BY1C24 Core Loading Plan and CPIX 0

Miscellaneous DRP 17-040 Revise UFSAR Section 15.6.2.2 to Correct CVCS Line Break 0

Location Description

Procedures LS-AA-104-1000 50.59 Resource Manual 14

6