IR 05000348/2022004

– Integrated Inspection Report 05000348/2022004 and 05000364/2022004

ML23017A066
Person / Time
Site:	Farley
Issue date:	01/23/2023
From:	Alan Blamey NRC/RGN-II/DRP/RPB2
To:	Gayheart C Southern Nuclear Operating Co
References
IR 2022004
Download: ML23017A066 (1)

Text

January 23, 2023

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000348/2022004 AND 05000364/2022004

Dear Cheryl Gayheart:

On December 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Joseph M. Farley Nuclear Plant. On January 19, 2023, the NRC inspectors discussed the results of this inspection with Mr. John Andrews, 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, Alan J. Blamey, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket Nos. 05000348 and 05000364 License Nos. NPF-2 and NPF-8

Enclosure:

As stated,

Inspection Report

Docket Numbers: 05000348 and 05000364

License Numbers: NPF-2 and NPF-8

Report Numbers: 05000348/2022004 and 05000364/2022004

Licensee: Southern Nuclear Operating Company, Inc.

Facility: Joseph M. Farley Nuclear Plant

Location: Columbia, AL

Inspection Dates: October 01, 2022, to December 31, 2022

Inspectors: B. Caballero, Senior Operations Engineer J. Diaz-Velez, Senior Health Physicist S. Downey, Senior Reactor Inspector P. Meier, Senior Resident Inspector B. Pursley, Health Physicist J. Rivera, Health Physicist S. Temple, Resident Inspector

Approved By: Alan J. Blamey, Chief Reactor Projects Branch 2 Division of Reactor Projects

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Joseph M. Farley Nuclear Plant, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

None.

PLANT STATUS

Unit 1 began the inspection period in refueling outage cycle 31 (1R31). On December 21, 2022, unit 1 reactor was taken critical and entered mode 1 on December 22, 2022. Over a period of approximately six days rated thermal power (RTP) was increased with various hold points for testing until December 28, 2022, when unit 1 achieved approximately 100 percent RTP. Unit 1 remained at approximately 100 percent RTP through the end of the report period.

Unit 2 began the report period at approximately 100 percent RTP and remained at or near 100 percent RTP through the end of the report 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 activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. 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.

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (2 Samples)

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

(1) Unit 2 'B' emergency diesel generator during the 1-2A emergency diesel generator maintenance outage on October 12, 2022 (per procedure FNP-0-SOP-38.0E)

(2) Unit 1 'B' emergency diesel generator on November 8, 2022, following maintenance (FNP-0-SOP-38.0-1B)

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)

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

(1) Unit 1 containment (FA 1-055) on October 12, 2022 (FNP-1-FPP-3.0)

(2) Unit 2 auxiliary building 121-foot elevation (non-radiation controlled area) corridor and hallway (FA 2-020) on November 2 and 3, 2022 (FNP-2-FPP-1.0, FNP-0-SOP-0.4)

(3) Unit 2 auxiliary building rod control system cabinet room (FA 2-023) on November 2 and 3, 2022 (FNP-2-FPP-1.0, FNP-0-SOP-0.4)

(4) Unit 2 auxiliary building communication room (FA 2-015) on November 2 and 3, 2022 (FNP-2-FPP-1.0, FNP-0-SOP-0.4)

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

(1) The inspectors evaluated pressurized water reactor non-destructive testing by reviewing the following examinations from September 26 to September 30, 2022:

1. Magnetic Particle Examination a. Weld 1F, flange to pipe weld, American Society of Mechanical Engineers (ASME) Class 3. This included a review of the associated welding activities.

b. Weld 2F, flange to pipe weld, ASME Class 3. This included a review of the associated welding activities.

2. Ultrasonic Examination a. Weld APR-4102-11-RB, pipe to elbow weld, ASME Class 1 b. Weld APR-4102-12-RB, pipe to pipe weld, ASME Class1 c.

Weld APR-4103-3-RB, pipe to elbow weld, ASME Class 1 d. Weld APR-4103-4-RB, valve to pipe weld, ASME Class 1 3. Visual Examination a. ALA1-1300-BMV, reactor pressure vessel closure head outside surface, ASME Class 1 b. ALA1-1300-S07, reactor vessel stud, ASME Class 1 c.

ALA1-1300-S08, reactor vessel stud, ASME Class 1 d. ALA1-1300-S09, reactor vessel stud, ASME Class 1

The inspector also evaluated the licensees boric acid control program performance.

71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance

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

(1) On June 16, 2022, the licensee completed administration of the biennial written examination and on July 14, 2022, the licensee completed administration of the annual requalification operating tests, which are both required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), "Requalification Requirements," of the NRC's "Operator's Licenses." During the week of December 19, 2022, the inspector performed an in-office review of the overall pass/fail results of the individual written examinations/operating tests and the crew simulator operating tests in accordance with IP 71111.11, "Licensed Operator Requalification Program." These results were compared to the thresholds established in Section 3.03, "Requalification Examination Results," of IP 71111.11.

The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating tests and biennial written examinations, which the licensee completed administering on July 14, 2022.

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 for the following activities:

Unit 1 safety injection system venting and preparations for draining the reactor cavity during the 1R31 refueling outage on October 5, 2022 Unit 2 operator testing of the '2B' emergency diesel generator on October 24, 2022 Unit 1 operator testing of the '1-2A' emergency diesel generator on December 17, 2022

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

(1) The inspectors observed and evaluated a licensed operator simulator exam scenario involving a loss of offsite power on November 14, 2022 (Segment 22-6 As-found).

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (1 Sample)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:

(1) Unit 1 'A' train main steam line mechanical snubber functional failure on September 21, 2022 (condition report (CR) 10909182)

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 risk during the '1-2A' emergency diesel generator planned maintenance outage on October 11 and 12, 2022 (NMP-DP-001)

(2) Alignment of the unit 2 'C' battery charger to the 'B' train during the unit 2 'B' battery charger testing resulting in yellow risk on October 18, 2022 (NMP-DP-001)

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)

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

(1) Unit 1 'B' emergency diesel generator following testing failures during loss of offsite power testing on September 20, 2022 (CR 10908660)

(2) Unit 1 'C' battery charger breaker EE06 failures during loss of offsite power testing on September 20 and 26, 2022 (CRs 10908663 and 10910364)

(3) Unit 1 'B' main feedwater stop valve disc failure discovered during the 1R31 refueling outage identified on October 3, 2022 (CR10912066)

(4) Unit 1 'B' emergency diesel generator fuel oil transfer pumps degraded performance identified on November 10, 2022 (CR10922488)

(5) Unit 1 computer room fire door (door 208) discovered propped open with no fire permit identified on December 13, 2022 (CR10931209)

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)

The inspectors evaluated the following temporary or permanent modifications:

(1) Unit 1 'B' start-up transformer replacement performed during the 1R31 refueling outage from September 18 to November 12, 2022 (SNC1141168)

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)

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

(1) Unit 1 reactor trip breaker rebuild and replacement in September 2022 during the unit 1 refueling outage 1R31 (work orders (WOs) SNC1082896, SNC984682)

(2) Unit 1 'B' start-up transformer pothead replacement completed in October 2022 during the unit 1 refueling outage 1R31 (WO SNC1230797)

(3) 1-2A emergency diesel generator testing following planned replacement and upgrade of the start-up relays that was completed on October 13, 2022 (WO SNC1190637)

(4) Unit 1 'B emergency diesel generator testing following breaker DG08 replacement on October 26, 2022 (FNP-0-SOP-38.0-1B, WO SNC1185459)

(5) Unit 2 'B' emergency diesel generator testing following J-relay replacements on November 30, 2022 (WOs SNC1190636, SNC1290654)

(6) Liquid penetrant examination and ASME pressure testing of a weld repair on the unit 1 reactor vessel inner O-ring leak-off pipe completed on December 18, 2022 (WOs SNC1415556, SNC981278)

71111.20 - Refueling and Other Outage Activities

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

(1) The inspectors evaluated unit 1 refueling outage 1R31 activities from September 16, 2022, to December 23, 2022.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:

Surveillance Tests (other) (IP Section 03.01) (2 Samples)

(1) Unit 1 B train safety injection with loss of offsite power test on September 26, 2022 (FNP-1-STP-40.0B)

(2) Unit 1 containment integrated leak rate test performed during the 1R31refueling outage on the week of September 19, 2022 (FNP-1-STP-117.0)

Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) Unit 1 containment purge supply and exhaust penetrations (pen 12 and 13) local leak rate testing performed on October 12, 2022 (FNP-1-STP-627)

71124.01 - Radiological Hazard Assessment and Exposure Controls

Radiological Hazard Assessment (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated how the licensee identified the magnitude and extent of radiation levels and the concentration and quantity of radioactive materials; and how the licensee assessed radiological hazards during the unit 1 refueling outage (1R31).

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

(1) The inspectors evaluated how the licensee instructed workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards during the 1R31 refueling outage.

Contamination and Radioactive Material Control (IP Section 03.03) (3 Samples)

The inspectors observed/evaluated the following licensee processes for monitoring and controlling contamination and radioactive material:

(1) Licensee surveys of potentially radioactive material leaving the auxiliary building at the unit 2 north missile shield door.

(2) Workers exiting the radiological controlled area (RCA) exit during the 1R31 refueling outage.

(3) Licensee surveys of potentially contaminated material leaving the unit 1 containment building equipment hatch during 1R31 refueling outage.

Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)

The inspectors evaluated the licensee's control of radiological hazards for the following radiological work:

(1) ALARA Work Package for Radiation Work Permit (RWP) 22-1463, "Reactor Head Lift and Set (Locked High Radiation Area (LHRA) Access)

(2) ALARA Work Package for RWP 22-1465, "Upper Internals Lift and Set (LHRA Access)

(3) ALARA Work Package for RWP 22-1504, "Refueling Activities"

High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (3 Samples)

The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas during refueling outage 1R31:

(1) LHRA controls for the unit 1 regenerative heat exchanger room in containment.

(2) LHRA controls for the unit 1 reactor cavity drain piping regenerative heat exchanger room in containment.

(3) Very High Radiation Area controls for access to the unit 1 normal reactor sump in containment.

Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)

(1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

Permanent Ventilation Systems (IP Section 03.01) (1 Sample)

The inspectors evaluated the configuration of the following permanently installed ventilation systems:

(1) Control room ventilation system, B train

Temporary Ventilation Systems (IP Section 03.02) (1 Sample)

The inspectors evaluated the configuration of the following temporary ventilation systems:

(1) Portable high efficiency particulate air (HEPA) unit no. 10

Use of Respiratory Protection Devices (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated the licensees use of respiratory protection devices.

Self-Contained Breathing Apparatus for Emergency Use (IP Section 03.04) (1 Sample)

(1) The inspectors evaluated the licensees use and maintenance of self-contained breathing apparatuses.

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 how the licensee processes, stores, and uses external dosimetry.

Internal Dosimetry (IP Section 03.03) (3 Samples)

The inspectors evaluated the following internal dose assessments:

(1) Internal dosimetry calculations for dose intake suspected on March 23, 2021 (ingestion pathway).

(2) Internal dosimetry calculations for dose intake suspected on April 01, 2021 (inhalation pathway).

(3) Internal dosimetry calculations for dose intake suspected on April 26, 2022 (inhalation pathway).

Special Dosimetric Situations (IP Section 03.04) (3 Samples)

The inspectors evaluated the following special dosimetric situations:

(1) Declared Pregnant Worker declared on March 16, 2021.

(2) Declared Pregnant Worker declared on October 12, 2021.

(3) Declared Pregnant Worker declared on December 2, 2021.

71124.05 - Radiation Monitoring Instrumentation

Walkdowns and Observations (IP Section 03.01) (9 Samples)

The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:

(1) Area radiation monitors in units 1 and 2 chemistry primary sample labs.

(2) Area radiation monitors in the unit 1 reactor containment building including the containment high range monitors during the 1R31 refueling outage.

(3) Observed functional test of portable ion chambers stored ready for use during 1R31 refueling outage.

(4) Portal monitors at the RCA exit and at the exit from the plant protected area.

(5) Observed calibration and functional tests of the small article monitors at the RCA exit and the hot tool room.

(6) Germanium detectors used in the primary chemistry laboratories for evaluating effluent and reactor coolant samples.

(7) Whole-body counter in the dosimetry office.

(8) Observed functional test of the plant vent radiation monitor.

(9) Observed functional test personnel contamination monitors at the RCA exit.

Calibration and Testing Program (IP Section 03.02) (12 Samples)

The inspectors evaluated the calibration and testing of the following radiation detection instruments:

(1) High Purity Germanium Detector 1 Liter Liquid Calibration and Calibration Confirmation, Detector #1, 09/14/2022

(2) LabLogic HIDEX 300SL RQ Liquid Scintillation Counter, serial number (SN) 2140428, 10/25/2018

(3) GEM 5 Portal Monitor at RCA Exit, SN 111-188 HP-GSD-027, 09/01/2022

(4) WOs SNC743129 and SNC 877538, calibrations of unit 1 containment high range ionization chambers, 10/09/2019 and 04/15/2021

(5) ARGOS 5AB at the RCA exit, SN HP-IPC-035A, 03/16/2022

(6) Ludlum Model 54 Small Article Monitor at RCA exit, SN HP-GSD-005, 04/21/2021

(7) Hopewell Designs Incorporated G10-2-2600-3XR Box Calibrator, 10/28/2021

(8) Standup whole-body counter in the auxiliary building, 06/21/2022

(9) Radeco Air Sampler, SN EP-HAS-025, 01/4/2022

(10) AMS-4 Continuous Air Monitor, SN HP-LAS-134, 02/22/2022

(11) Mirion Telepole Extendable Geiger-Mueller (GM) survey meter, SN HP-GMT-297, 09/14/2021

(12) Ludlum Model 9-3, SN HP-IOC-211, 10/21/2021

Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (2 Samples)

The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:

(1) WO SNC1011285, RE0018 - unit 2 liquid waste effluent processing monitor, 05/01/2020

(2) WOs SNC1012619 and SNC1079717, RE0029B - unit 1 plant vent stack gas monitor, 03/03/2020 and 06/30/2021

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

MS06: Emergency AC Power Systems (IP Section 02.05)===

(1) Unit 1 (October 1, 2021 - September 30, 2022)

(2) Unit 2 (October 1, 2021 - September 30, 2022)

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

(1) Unit 1 (October 1, 2021 - September 30, 2022)

(2) Unit 2 (October 1, 2021 - September 30, 2022)

MS08: Heat Removal Systems (IP Section 02.07) (2 Samples)

(1) Unit 1 (October 1, 2021 - September 30, 2022)

(2) Unit 2 (October 1, 2021 - September 30, 2022)

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

(1) April 1, 2021, through September 6, 2022 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)

(1) April 1, 2021, through September 6,

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 29, 2022, the inspectors presented the baseline in-service inspection results to Mr. Delson Erb, Site Vice President, and other members of the licensee staff.

On October 5, 2022, the inspectors re-exited the baseline in-service inspection results to Mr. Ronnie G. Surber, Licensing Manager, and other members of the licensee staff.

On October 25, 2022, the inspectors presented the occupational radiation safety baseline inspection results to Mr. Ronnie G. Surber, Licensing Manager, and other members of the licensee staff.

On January 19, 2023, the inspectors presented the integrated inspection results to Mr.

John Andrews, Plant Manager, and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.08P Corrective Action CRs (By Number) 10882988, 10884035, 10891419, 10892523, 10897076,

Documents 10902518, 10909830

Corrective Action CRs (by number) 10910709, 10912544

Documents

Resulting from

Inspection

NDE Reports 22FNP1V002 Visual Examination of Reactor Vessel Stud ALA1-1300-S07 10/04/2022

2FNP1V003 Visual Examination of Reactor Vessel Stud ALA1-1300-S08 10/04/2022

2FNP1V004 Visual Examination of Reactor Vessel Stud ALA1-1300-S09 10/04/2022

F22FNP1UT014 Ultrasonic Examination of Weld ALA1-4103-3-RB 10/05/2022

F22FNP1UT015 Ultrasonic Examination of Weld ALA1-4102-11-RB 10/10/2022

F22FNP1UT016 Ultrasonic Examination of Weld ALA1-4102-12-RB 10/10/2022

F22FNP1UT022 Ultrasonic Examination of Weld ALA1-4103-4-RB 10/04/22

F22FNP1V029 Visual Examination of RPV Closure Head Outside Surface 10/01/2022

71124.03 Corrective Action CR10911436 Math errors with respirator use evaluation worksheet

Documents CR10911440 CR could not be found for B train Control Room Ventilation

Resulting from Unit paint chipping

Inspection

Miscellaneous 22-1437 NMP-HP-204-F06, Respirator Use Evaluation Worksheet, 09/14/2022

Incore Detector and Drive Box Change Out

20823029-01 TRI Air Testing, Laboratory Report, Compressed Air/Gas 08/23/2022

Quality Testing

GG2.234 Monthly In-Service SCBA Cylinder Surveillance 08/31/2022

HP-NPU-010 HEPA Unit Test Data 01/04/2022

Procedures F-FP-LP-DLA002 Self-Contained Breathing Apparatus: General User Dynamic Version 1.1

Learning Activity (DLA)

FNP-0-RCP-110 Sampling of Service Air to Meet Respiratory Limits Version 14.0

NMP-HP-305 Alpha Radiation Monitoring Version 5.11

NMP-HP-501 Radiological Respiratory Protection Program Version 1.5

NMP-HP-501-004 Inspection, Repair and Storage of Self-Contained Breathing Version 1.7

Apparatus

NMP-HP-515 M Versaflo Powered Air Purifying Respirator (PAPR) Use and Version 2.0

Inspection Type Designation Description or Title Revision or

Procedure Date

Control

Work Orders SNC1083429 B TRN CONTROL RM VENTILATION TEST 07/25/2022

SNC1086094 B TRN CONTROL ROOM EMERGENCY VENTILATION 07/25/2022

CHARCOAL

71124.05 Corrective Action CR10911446 Potential enhancement for RP SAM Calibration Procedure

Documents CR10911449 Comments on Air Sample Gamma Spectroscopy Libraries

Resulting from

Inspection

71151 Corrective Action 10910278 09/26/2022

Documents

Resulting from

Inspection

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