IR 05000348/2020004

Integrated Inspection Report 05000348/2020004 and 05000364/2020004 and Independent Spent Fuel Storage Installation Report 07200042/2020003

ML21042A000
Person / Time
Site:	Farley, 07200042
Issue date:	02/11/2021
From:	Alan Blamey Division Reactor Projects II
To:	Gayheart C Southern Nuclear Company
References
IR 2020003, IR 2020004
Download: ML21042A000 (21)

Text

February 11, 2021

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT - INTEGRATED INSPECTION REPORT 05000348/2020004 AND 05000364/2020004 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION REPORT 07200042/2020003

Dear Ms. Gayheart:

On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Joseph M. Farley Nuclear Plant. On January 28, 2021, the NRC inspectors discussed the results of this inspection with Charles Kharrl 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/

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

Docket Nos. 05000348 and 05000364 and 07200042 License Nos. NPF-2 and NPF-8

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000348 and 05000364 and 07200042

License Numbers:

NPF-2 and NPF-8

Report Numbers:

05000348/2020004, 05000364/2020004 and 07200042/2020003

Enterprise Identifier: I-2020-004-0041 and I-2020-003-0081

Licensee:

Southern Nuclear Company

Facility:

Joseph M. Farley Nuclear Plant

Location:

Columbia, AL

Inspection Dates:

October 1, 2020 to December 31, 2020

Inspectors:

J. Diaz-Velez, Senior Health Physicist

S. Downey, Senior Reactor Inspector

B. Kellner, Senior Health Physicist

B. Caballero, Senior Operations Engineer

S. Freeman, Senior Reactor Analyst

P. Meier, Senior Resident Inspector

K. Miller, Resident Inspector

W. Pursley, Health Physicist

N. Staples, Senior Project Engineer

S. Temple, Resident Inspector

Approved By:

Alan J. Blamey, Chief

Reactor Projects Branch 2

Division of Reactor Projects

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 report period at approximately 100 percent rated thermal power (RTP). On November 20, 2020, RTP was reduced to approximately 90 percent for planned turbine valve testing and restored to approximately 100 percent RTP on the following day. After the testing, unit 1 remained at or near 100 percent RTP through the end of the report period.

Unit 2 began the report period at approximately 100 percent RTP. On October 2, 2020, unit 2 began power coastdown for a planned refueling outage. On October 11, 2020, unit 2 was shut down and entered Mode 5 for the planned outage. Following the outage, on November 13, 2020, the unit 2 reactor was taken critical and entered mode 1 on November 14, 2020. Over a period of approximately four days, RTP was increased with various hold points for testing of the recently implemented measurement uncertainty recapture (MUR) modification. On November 18, 2020, RTP was increased and held at approximately 95% for additional MUR validation. On December 22, 2020, RTP was raised to approximately 99.3% and held there 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 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) (2 Samples)

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

(1) Unit 2 'B' train emergency diesel generator following safety injection and loss of offsite power testing during the unit 2 outage in October 2020 (FNP-0-SOP-38.0).

(2) Unit 2 'A' train residual heat removal system following restoration from the 'A' residual heat removal pump motor replacement in October 2020 (Dwg D205041).

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 0224-U1 for the unit 1 'A' train vital DC switchgear room on November 24, 2020 (FNP-1-FPP-1.0).

(2) Fire Zone 0343-U1 for the unit 1 'B' 4160 volt switchgear room on November 24, 2020 (FNP-1-FPP-1.0).

(3) Fire Zone 0334-U1 for the unit 1 'V' motor control center room on November 24, 2020 (FNP-1-FPP-1.0).

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

(1) The inspectors evaluated pressurized water reactor non-destructive testing by reviewing the following examinations from November 2 to November 6, 2020:

1. Magnetic Particle Examination

a. Weld APR2-3100-8R, 'A' steam generator feedwater nozzle to shell weld, ASME Class 2 b. Weld F1, 6 service water system pipe to elbow weld, ASME Class 3.

This included a review of associated welding activities c. Weld F2, 6 service water system pipe to elbow weld, ASME Class 3.

This included a review of associated welding activities

2. Ultrasonic Examination

a. Weld APR1-1100-1, reactor pressure vessel (RPV) flange to upper shell weld, ASME Class 1 b. Weld APR1-1100-5, RPV intermediate to lower shell weld, ASME Class 1 c. Weld APR1-4100-1DM, RPV outlet nozzle to safe-end weld, ASME Class 1 d. Weld APR2-3100-8R, 'A' steam generator feedwater nozzle to shell weld, ASME Class 2

3. Visual Examination

a. Bare metal visual of weld APR1-4100-1DM, RPV outlet nozzle to safe-end weld, ASME Class 1 b. VT-3 of RPV interior surfaces, ASME Class 1

The inspectors 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)

The licensee completed the annual requalification operating test and biennial written examination 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 NRCs Operators Licenses. During the week of December 14, 2020, the inspector performed an in-office review of the overall pass/fail results of the individual operating examinations, the crew simulator operating examinations, and the biennial written examinations in accordance with Inspection Procedure (IP) 71111.11, Licensed Operator Requalification Program. These results were compared to the thresholds established in Section 3.02, Requalification Examination Results, of IP 71111.11.

(1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification biennial written exam, and the administration of the annual operating test which was completed by the licensee on December 11, 2020.

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 a unit 2 downpower in preparation for the unit 2 refueling outage on October 11, 2020.

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

(1) The inspectors observed licensed operator training on the simulator involving shut-down evolutions, on October 6, 2020, in preparation for the unit 2 fall outage (FNP-2-UOP-2.4).

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 component cooling water heat exchanger leakage identified on September 29, 2020 (CR 10742170).

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 1 risk with the unit 1 'B' train emergency diesel generator inoperable during the service water repair to the piping connecting unit 1 and unit 2 service water return from the respective 'B' train emergency diesel generators on November 5 and 6, 2020 (NMP-GM-031).

(2) Unit 1 risk during 1-2A emergency diesel generator testing and switchyard work on November 19, 2020 (NMP-GM-031).

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (2 Samples)

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

(1) Gas voiding in the unit 1 'A' train residual heat removal system discharge piping identified on September 16, 2020 (CR 10739390).

(2) Unit 2 'A' train reactor trip breaker closing issue identified on November 8, 2020 (CR

===10752401).

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) Implementation of the unit 2 measurement uncertainty recapture using the leading edge flow measurement system installed during the unit 2 outage in October and November, 2020 (DCP SNC971518).

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01)===

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

(1) Number 4 service water battery cell replacement on August 26, 2020 (WO SNC1110541).

(2) Unit 2 'A' train residual heat removal pump motor replacement during the unit 2 refueling outage in October, 2020 (WO SNC633690).

(3) Unit 2 'C' service water pump and 'A' train header isolation valve (Q2P16V507).

replacement during the unit 2 outage in October, 2020 (SNC1012385; 1126422).

(4) Unit 2 'B' emergency diesel generator service water return line leak repair performed during the unit 2 outage on November 5 and 6, 2020 (WO SNC1121637).

71111.20 - Refueling and Other Outage Activities

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

(1) The inspectors evaluated unit 2 refueling outage 27 from October 11, 2020 - November 15, 2020 (FNP-0-UOP-4.0).

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

(1) Unit 2 turbine auxiliary feedwater pump comprehensive test on October 8, 2020 (FNP-2-STP-22.32).

(2) Unit 2 reverse flow test of the refueling water storage tank to charging pump check valve performed on October 16, 2020 (FNP-2-STP-4.10).

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

(1) Unit 2 containment purge exhaust and supply penetration as-left local leak rate testing during the unit 2 outage before mode 4 entry on November 6, 2020 (FNP-2-STP-627).

71114.06 - Drill Evaluation

Drill/Training Evolution Observation (IP Section 03.02) (1 Sample)

The inspectors evaluated:

(1) A licensed operator continuing training simulator scenario that included a drill and exercise performance indicator opportunity involving a loss of all A/C power on November 23, 2020 (LOCT As-Found 20-7).

71124.01 - Radiological Hazard Assessment and Exposure Controls

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

(1) The inspectors evaluated how the licensee identifies the magnitude and extent of radiation levels and the concentrations and quantities of radioactive materials and how the licensee assesses radiological hazards.

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

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

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

The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.

(1) Observed licensee surveys of potentially contaminated material leaving the RCA.

(2) Observed workers exiting the Unit 2 containment [contaminated area] during a refueling outage.

(3) Observed workers exiting the RCA at the main RCA exit point during a refueling outage.

Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)

The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.

(1) Reactor Vessel Nozzle Inspection Mechanical Stress Improvement Process [Locked High Rad Area (LHRA)/High Risk] under RWP 20-2783, Revisions 0 and 1.

(2) Incore Drive Box Maintenance [High Rad Area/High Risk] under RWP 20-2437, Revision 0.

(3) Reactor Head Lift [LHRA/High Risk] under RPW 20-2463, Revision 0.

(4) Reactor Upper Internals Lift [LHRA/High Risk] under RPW 20-2465, Revision 0.

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:

(1) Unit 2 Containment Sump Door [Very High Rad Area/Grave Danger].

(2) Unit 2 Containment Regenerative Heat Exchanger Fence [LHRA].

(3) Unit 1 Volume Control Tank Room [LHRA].

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) (2 Samples)

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

(1) Solidification Dewatering Facility Vent Blower System.

(2) Fuel Handling Area Heating, Ventilating and Filtration System.

Temporary Ventilation Systems (IP Section 03.02) (2 Samples)

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

(1) HEPA Unit #HP-NPU-001 in Unit 2 Reactor Cavity for the Mechanical Stress Improvement Process project.

(2) HEPA Unit #HP-NPU-012 in Unit 2 containment building at the seal table.

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 licensee performance as it pertains to external dosimetry that is used to assign occupational dose.

Internal Dosimetry (IP Section 03.03) (2 Samples)

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

(1) DAC-Hr assignments for individuals potentially exposed to airborne tritium during work in the 1C charging pump cubicle on 07/31/2018, Radiological Survey #132065

(2) DAC-Hr assignments for individuals potentially exposed to airborne tritium during work in the 1A charging pump cubicle on 06/05/2020, Radiological Survey #143779

Special Dosimetric Situations (IP Section 03.04) (2 Samples)

The inspectors evaluated the following special dosimetric situations:

(1) Extremity monitoring results for plant ID #2283 for period 01/01/2020 - 06/30/2020

(2) Inspector review of licensee data determined that there were no other exposure events (skin dose, multi-badging, etc.) that occurred during the period covered by the inspection. Additionally, there were no declared pregnant workers monitored during the inspection period.

71124.05 - Radiation Monitoring Instrumentation

Walkdowns and Observations (IP Section 03.01) (10 Samples)

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

(1) Area radiation monitors in the main control room, the primary chemistry sample lab and the technical support center

(2) Area radiation monitors in the U2 containment building including the containment high range monitors.

(3) Portable ion chambers stored ready for use and/or during use in U2 containment

(4) Extendable GM detectors stored ready for use and/or during use in U2 containment

(5) Personal contamination monitors in use at the exit to the radiologically controlled area and the waste solidification and dewatering building.

(6) Portal monitors in use at the radiological controlled area exit and the exit from the protected area.

(7) Continuous air monitors and air samplers in the auxiliary building and U2 containment.

(8) Alpha and Beta smear counters in the radiation protection sample counting lab.

(9) High Efficiency Germanium Detectors in the Chemistry lab.

(10) Portable neutron survey instruments stored "ready for use" in the radiation protection instrument lab.

Calibration and Testing Program (IP Section 03.02) (14 Samples)

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

(1) Ludlum 2000, Sn#291351

(2) GMT Telepole, Sn#6699-028

(3) RM-20, Sn#268

(4) Ludlum 3A, Sn#260678

(5) Canberra GEM-5, Sn#0911-194

(6) SAM-12, Sn#HP-GSD-028A

(7) RO-2, Sn#580

(8) ARGOS 5AB, Sn#HP-IPC-035A

(9) ABPM 203, Sn#HP-LAS-096A

(10) AMS 4, Sn#HP-LAS-103B

(11) LoVOL, Sn#10614

(12) Mirion Series XLB Proportional Counter, Sn#HP-LBC-001B

(13) Ludlum 30, Sn#25017758

(14) Canberra iSolo Alpha/Beta Counter, Sn#6059155

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) UNIT 1 - N1D11RI0013 - GAS DECAY TANKS TO WPS RADIATION MONlTOR (Work Order # SNC678783).

(2) UNIT 1 - NID21RE0002 - CONTAINMENT RADIATION MONITOR (Work Order #

SNC772653 ).

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 (November 1, 2019 - October 31, 2020).

(2) Unit 2 (November 1, 2019 - October 31, 2020).

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

(1) Unit 1 (November 1, 2019 - October 31, 2020).

(2) Unit 2 (November 1, 2019 - October 31, 2020).

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

(1) Unit 1 (November 1, 2019 - October 31, 2020).

(2) Unit 2 (November 1, 2019 - October 31, 2020).

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

(1) March 2019 to September 2020.

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) March 2019 to September

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

2515/194 - Inspection of the Licensees Implementation of Industry Initiative Associated With the Open Phase Condition Design Vulnerabilities In Electric Power Systems (NRC Bulletin 2012-01)

Revision 0 of this TI was previously inspected, and closed, in Inspection Report 2019012 (ADAMS ML19240A829). However, a subsequent revision to the NEI Voluntary Initiative (Revision 3) provided plants the option to leave the open phase protection (OPP) system in monitoring mode only in lieu of activating the automatic trip circuitry, provided it was supported by a risk evaluation. Revision 1 (and later Revision 2) of this TI was issued to provide inspection guidance for the new option.

The inspectors reviewed licensee analyses and procedures that demonstrated operator manual actions would successfully mitigate the impact of an Open Phase Condition (OPC). The analyses were reviewed remotely, and the procedures were reviewed and walked down on site. The inspectors completed Section 03.01c of TI 2515/194, Revision 2.

The inspectors verified that modeling used for the OPC reflected the as-designed and as-built plant, assumptions made by the licensee were reasonable, and licensee procedures were adequate to successfully respond to an OPC. The inspectors also verified that human reliability analysis and recovery evaluations were done in accordance with NEI and voluntary initiative guidance.

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

(1) Verified that routine activities are performed in accordance with approved procedures and surveillance activities have been conducted at the specified periods on December 7, 2020 (FNP-0-STP-63.7).

===92702 - Follow-Up on Traditional Enforcement Actions Including Violations, Deviations, Confirmatory Action Letters, and Orders

Follow-Up on Traditional Enforcement Actions Including Violations, Deviations, Confirmatory Action Letters, and Orders===

(1) On November 20, 2019, as a result of Alternative Dispute Resolution the NRC issued Confirmatory Order (CO) EA-18-130 and EA-18-171 (ML19249B552). The CO was the result of an apparent violation of 10 CFR 53.5, Employee Protection at Vogtle Units 3 & 4 which contained actions for the Farley, Hatch and Vogtle Units 1 & 2 nuclear plants. During the week of November 30,2020, the inspectors reviewed corrective actions for this CO. Because the CO was fleet wide for the Southern Nuclear Company, the corrective actions reviewed by the inspectors included a review of corrective actions for the Hatch, Farley, and Vogtle Units 1 through 4 nuclear plants. The details can be found in inspection report 0500025/20200012, 0500026/2020012; 11/30/2020 through 12/11/2020; Vogtle Unit 3 Combined License, Vogtle Unit 4 Combined License, CO Follow-Up and SCWE inspection report.

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

• On January 28, 2021, the inspectors presented the integrated inspection results to Charles Kharrl and other members of the licensee staff.

• On October 23, 2020, the inspectors presented the Radiation Safety Inspection Licensee Debrief inspection results to D. Erb and other members of the licensee staff.

• On November 5, 2020, the inspectors presented the ISI Exit Meeting inspection results to Chuck Kharrl, Site Vice President and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

2515/194

Calculations

PRA-BC-F-19-

004

FNP Open Phase Condition Evaluation

VERSION 1

Procedures

FNP-1-AOP-5.2

DEGRADED GRID

Revision

20.0

FNP-1-ARP-1.12

Main Control Board Annunciator Panel M

VERSION

77.1

FNP-1-ARP-5.0

Unit Startup Transformers Miscellaneous Alarm Panel

VERSION

15.1

FNP-2-AOP-5.2

DEGRADED GRID

Revision

20.0

FNP-2-ARP-1.12

Main Control Board Annunciator Panel M

VERSION

54.2

FNP-2-ARP-5.0

Unit Aux, Startup Transformers Miscellaneous Alarm Panel

VERSION

11.1

NMP-OS-007-001 Conduct of Operations Standards and Expectations

VERSION

17.0

NMP-OS-007-005 Site Specific Operations Expectations and Fleet Operations

Policies

VERSION

1.0

71111.08P Miscellaneous

Procedure

Qualification

Record B025

GTAW/Manual

2/11/1977

Welding

Procedure

Specification

1.20N

Gas Tungsten Arc Welding/Manual

Revision 3

NDE Reports

S20F2M001

Magnetic Particle Examination Report - Steam Generator A

Feedwater Nozzle to Shell Weld

10/24/2020

S20F2U036

Ultrasonic Examination Report - Steam Generator A

Feedwater Nozzle to Shell Weld

10/24/2020

S20F2V073

Visual Examination Report - RPV Hot Leg Safe End

10/24/2020

Procedures

NMP-ES-019-001

Boric Acid Corrosion Control Program Implementation

Version 11.1

NMP-ES-024-202

Visual Examination (VT-2)

Version 7.0

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

NMP-ES-024-401

Magnetic Particle Examination

Version 12.0

NMP-ES-024-516

Manual Ultrasonic Examination of Pressure Vessel Welds

(Non-Appendix VIII)

Version 6.0

71124.01

ALARA Plans

RWP 20-4403

POST-JOB ALARA REVIEW

RWP 20-4403 Used Fuel Loading Outage Activities [HRA,

medium risk]

04/13/2020

Calculations

DAW 091719-V

WMG Dry Active Waste Characterization

2/04/2019

Corrective Action

Documents

CR #'s 10514682,

10553279,

10576745,

10598558,

10603243,

10605457,

10649744,

10652543,

10674501, &

10746334

Sampling of Radiation Safety Related CRs written by the

Licensee during the inspection period being reviewed

Various

Corrective Action

Documents

Resulting from

Inspection

10747961

Radioactive Source Handling Practices

10/21/2020

Miscellaneous

Radioactive Source Inventory List [Radioactive Standard

Inspection and Inventory Check Report]

05/11/2020

FNP Radiation Protection Exposure Report [Daily,

departmental, RWP, & YTD dose, and contamination events]

10/20/2020

1st thru 3rd

Quarter 2020

Joseph M Farley Nuclear Plant Open EMS Report - Doses

to a member of the public due to Gaseous Releases

09/28/2020

Air Sample ID #

240823

Air Sample Gamma Spectroscopy Result - U2 Lower Cavity

Flange

10/14/2020

Air Sample ID #

240781

Air Sample Gamma Spectroscopy Result - CTMNT-2

Transfer Canal Inspection

10/13/2020

Air Sample ID #

240972

Air Sample Gamma Spectroscopy Result - U2 Reactor Head

Lift

10/15/2020

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Air Sample ID #

241251

Air Sample Gamma Spectroscopy Result - U2 Upper Cavity

GA During Cavity Decon

10/20/2020

Radiation

Protection Shift

Turnover

Day Shift to Night Shift and Night Shift to Day Shift -

10/19/2020 thru 10/23/2020

Various

Procedures

FNP-2-STP-

27.18

In-Containment High Range Radiation Area Monitor

Q2D21RE0027A

Version 24

NMP-GM-002

Corrective Action Program

Version 15.2

NMP-GM-002-

001

Corrective Action Program Instructions

Version 39.0

NMP-HP-108

Issuance, Use and Collection of Personnel Dosimetry

09/16/2020

NMP-HP-201

Personnel Dosimetry Program

11/12/2019

NMP-HP-202

Radiological Controls for Highly Radioactive Objects

10/30/2019

NMP-HP-300

Radiation and Contamination Surveys

Version 5.5

NMP-HP-302-001

Radiological Key Control

Version 3.3

NMP-HP-306

Radiological Job Coverage

Version 1.1

NMP-HP-400

Control and Accountability of Radioactive Sources

Version 3.14

Radiation

Surveys

Survey # 144186

Negative Pressure Unit Inventory

07/08/2020

Survey # 144606

Annual Source Inventory Survey

08/07/2020

Survey # 145637

Semi Annual Sealed Leak Source Test

10/07/2020

Survey # 145684

U2 Containment 155' - Initial

10/11/2020

Survey # 145685

U2 Containment 105' O/S Biowall - Initial

10/11/2020

Survey # 145686

U2 Containment 105' I/S Biowall - Initial

10/11/2020

Survey # 145736

U-2 Reactor Cavity - Upper Initial survey

10/12/2020

Survey # 145738

U-2 Reactor head shield doors posted LHRA

10/12/2020

Survey # 145754

U-2 Reactor head after insulation removal

10/12/2020

Survey # 145761

U-2 Aux Bldg 121' - Post Crud Burst

10/12/2020

Survey # 145766

U-2 Aux Bldg 100' - Post Crud Burst

10/12/2020

Survey # 145766

U-2 Aux Bldg 83' - Post crud burst

10/12/2020

Survey # 145795

U-2 Pressurizer - All elevations

10/13/2020

Survey # 145804

U2 Containment Transfer Canal

10/13/2020

Survey # 145827

U-2 Seal Table

10/13/2020

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Survey # 145831

U2 CTMNT x-fer canal blind flange

10/14/2020

Survey # 146106

Move upper internals to vessel

10/19/2020

Survey # 146130

Waste Evaporator Feed Filter Changeout

10/20/2020

Survey # 146143

U2 Reactor Cavity

10/20/2020

Radiation Work

Permits (RWPs)

RWP 20 -2463

Reactor head lift and set in support of the outage [LHRA

Access, high risk]

Revision 0

RWP 20-2101

Administration Activities by ADM, SEC, IT, NOS, S&H, NRC,

INPO, TRN, PI, Work MGM, Containment Coordinators &

O&S personnel... [HRA Access, Medium Risk]

Revision 0

RWP 20-2301

Radiation Protection Activities to support work in High

Radiation Areas [HRA Access, Medium Risk]

Revision 0

RWP 20-2435

Incore drive box maintenance and grooming [HRA Access,

medium risk]

Revision 0

RWP 20-2437

Incore drive box maintenance [HRA Access, high risk]

Revision 0

RWP 20-2783

Reactor Vessel Nozzle Inspection Mechanical Stress

Improvement Process [Locked High Rad Area(LHRA)/High

Risk]

Revisions 0

and 1

Self-Assessments TE# 1036107

Self-Assessment Topic/ Title: RP Occupational Inspection

04/28/2020

71124.03

Calibration

Records

FNP HEPA

ID#NPU-001

HEPA Unit Certification

2/05/2020

HP-VAC-033

Vacuum Certification for Vacuum #HP-VAC-033

01/04/2020

Corrective Action

Documents

CRs # 10105147,

10491521,

10516028,

10583566,

10619841, and

10719240

CRs # 10105147, 10491521, 10516028, 10583566,

10619841, and 10719240

Various

Miscellaneous

Breathing Air

Report

TRI Air Testing, INC Report #392-475-9 for Bauer

Compressed Air System

06/01/2020

Breathing Air

Report

TRI Air Testing, INC Report #398-740-1 for Bauer

Compressed Air System

08/20/2020

List of MSA

SCBA Users

List of MSA SCBA Users (Including Qualifications and

Curriculum)

09/25/2020

NMP-HP-305

Farley Nuclear Plant Alpha Source Term Characterization

03/09/2020

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Report

Procedures

NMP-HP-301

Airborne Radioactivity Sampling and Evaluation

Rev. 4.2

NMP-HP-305

Alpha Radiation Monitoring

Rev. 5.11

NMP-HP-501

Radiological Respiratory Protection Program

Rev. 1.3

NMP-HP-501-001

Instruction for Selection and Use of Respiratory Protection

Equipment for Radiological Protection

Rev. 1.5

NMP-HP-501-002

Control, Issuance, and Return of Radiological Respiratory

Protection Equipment

Rev. 2.2

NMP-HP-501-003

Inspection, Repair, and Storage of Non-SCBA Respiratory

Protection Equipment

Rev. 1.1

NMP-HP-501-004

Inspection, Repair and Storage of Self-Contained Breathing

Apparatus

Rev. 1.6

NMP-HP-501-005

Inspection, Repair and Storage of the MSA G1 SCBA

Rev. 2.0

NMP-HP-504

Quantitative Fit Testing of Individuals For Respirator Use

Rev. 4.1 and

4.2

NMP-HP-509

Selection and Control of Portable Ventilation Units

Rev. 1.4

NMP-HP-515

3M Versaflo Powered Air Purifying Respirator (PAPR) Use

and Contro

Rev. 1.4

Radiation

Surveys

141676

Effectiveness Review of Respiratory Protection Program

01/03/2020

144828

Compressed Breathing Air Quality

08/20/2020

145183

Breathing Air Box Filter Changeout

09/15/2020

145346

Monthly Respiratory Protection Mask Inventory and

Inspection

09/25/2020

145581

Respiratory Equipment Surveillances

10/07/2020

145590

Vacuum Cleaner Inventory

10/07/2020

Self-Assessments 18-0444

Post-Job ALARA Review

2/31/2018

18-4403

Post-Job ALARA Review

11/09/2018

18-4404

Post-Job ALARA Review

11/09/2018

NMP-GM-003F18

(TE#1036107)

Check-In Self-Assessment (CISA)

07/06/2020

Work Orders

SNC1001016

B-train Penetration Room Filtration Performance Test

04/02/2020

SNC1001206

B TRN CONTROL ROOM EMERGENCY VENTILATION

CHARCOAL

04/03/2020

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

SNC992763

Control Room Emergency Ventilation Charcoal Absorber

Sampling and Testing

04/17/2020

SNC992767

Penetration Room Filtration Charcoal Absorber Sampling

and Testing

04/23/2020

SNC992769

A-train Penetration Room Filtration Performance Test

04/23/2020

SNC994900

Control Room Emergency Ventilation Performance Test for

A Train

04/17/2020

SNC998070

B TRN CONTROL RM VENTILATION TEST

04/03/2020

71124.04

Corrective Action

Documents

CRs # 10488412,

10494275,

10509743 and

10725840

CRs # 10488412, 10494275, 10509743 and 10725840

Various

Miscellaneous

DAW 091919-V

Dry Active Waste Sample Report

09/17/2019

Procedures

NMP-HP-100

Bioassay Program

Rev. 1.2

NMP-HP-101

In-Vivo Bioassay and Internal Dose Assessment

Rev. 3.1

NMP-HP-102

In-Vitro Bioassay

Rev. 1.2

NMP-HP-103

Skin Dose Assessment

Rev. 3.2

NMP-HP-104

Use and Calibration of Whole Body Counters

Rev. 4.1

NMP-HP-104-008

Resolving Unidentified Peaks and Assignment of Dose

Rev. 1.0

NMP-HP-104-009

Whole Body Counter Computer Startup, Logon and

Shutdown With Apex-InVivo

Rev. 3.2

NMP-HP-104-010

Whole Body Counter Daily Quality Control Checks With

Apex-InVivo

Rev. 2.0

NMP-HP-104-011

Performing Whole Body Counts Using Apex-InVivo

Rev. 3.2

NMP-HP-105

Comparison of OSLD and Ed Dosimetry Results

Rev. 1.4

NMP-HP-106

Investigation of Exposures Exceeding Fleet Administrative

Limits

Rev. 2.1

NMP-HP-108

Issuance, Use, and Collection of Personnel Dosimetry

Rev. 2.1

NMP-HP-108-001

Instructions for Issuing and Activating Dosimetry and

Updating Dose Records in HIS-20

Rev. 2.2

NMP-HP-108-002

Use of EDE (Effective Dose Equivalent) Methodologies

Rev. 3.2

NMP-HP-109

Investigation, Evaluation and Management of Damaged,

Lost, Malfunctioning or Alarming Dosimetry

Rev. 2.6

NMP-HP-201

Personnel Dosimetry Program

Rev. 2.6

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Radiation

Surveys

2H18

PERIMETER

OSL EXPOSURE

REPORT

2H18 PERIMETER OSL EXPOSURE REPORT

2/27/2019

71151

Corrective Action

Documents

Electronic Dosimeter Condition Reports: CR 10603790,

CR10657167, CR10657410, 10735779, & 10746697

Various

Miscellaneous

Electronic Dosimeter Dose and Dose Rate Alarm Logs

March 1, 2019 thru September 25, 2020

09/25/2020

1st thru 3rd

Quarter 2020

Joseph M Farley Nuclear Plant Open EMS Report - Doses

to a member of the public due to Liquid Releases

09/28/2020

1st thru 3rd

Quarter 2020

Joseph M Farley Nuclear Plant Open EMS Report - Doses

due to Radio-Iodines, Tritium, and Particulates in Gaseous

Releases

09/28/2020

1st thru 3rd

Quarter 2020

Joseph M Farley Nuclear Plant Open EMS Report - Air

Doses Due To Gaseous Releases

09/28/2020

1st thru 4th

Quarter 2019

2019 Joseph M Farley Nuclear Plant Open EMS Report -

Annual Radioactive Effluent Release Report, Air Doses Due

To Gaseous Releases

03/25/2020

1st thru 4th

Quarter 2019

2019 Joseph M Farley Nuclear Plant Open EMS Report -

Annual Radioactive Effluent Release Report, Doses to a

member of the public due to Liquid Releases

03/25/2020

1st thru 4th

Quarter 2019

2019 Joseph M Farley Nuclear Plant Open EMS Report -

Annual Radioactive Effluent Release Report, Doses due to

Radio-Iodines, Tritium, and Particulates in Gaseous

Releases

03/25/2020

Procedures

NMP-AD-029

Preparation and Reporting of Regulatory Assessment

Performance Indicator Data and the Monthly Operating

Report

Version 2.0

NMP-AD-034

Key Performance Indicators

Version 10.0