Text

Integrated Inspection Report 05000250/2021004 and 05000251/2021004
	ML22032A251
Person / Time
Site:	Turkey Point
Issue date:	02/02/2022
From:	David Dumbacher; NRC/RGN-II/DRP/RPB3
To:	Coffey B; Florida Power & Light Co
References
	IR 2021004
	Download: ML22032A251 (22)
	v • d • e

February 2, 2022

SUBJECT:

TURKEY POINT UNIT 3 & 4 - INTEGRATED INSPECTION REPORT 05000250/2021004 AND 05000251/2021004

Dear Mr. Coffey:

On December 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Turkey Point Unit 3 & 4. On January 26, 2022, the NRC inspectors discussed the results of this inspection with Mr. Michael Pearce, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.

One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. We are treating this violation as a non-cited violation (NCV), consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violation, or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC Resident Inspector at Turkey Point Unit 3 & 4.

If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; and the NRC Resident Inspector at Turkey Point Unit 3 & 4. 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/

David E. Dumbacher, Chief Reactor Projects Branch 3 Division of Reactor Projects

Docket Nos. 05000250 and 05000251 License Nos. DPR-31 and DPR-41

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000250 and 05000251

License Numbers: DPR-31 and DPR-41

Report Numbers: 05000250/2021004 and 05000251/2021004

Enterprise Identifier: I-2021-004-0034

Licensee: Florida Power & Light Company

Facility: Turkey Point Unit 3 & 4

Location: Homestead, FL 33035

Inspection Dates: October 1, 2021 to December 31, 2021

Inspectors: P. Cooper, Senior Reactor Inspector J. Diaz-Velez, Senior Health Physicist M. Endress, Senior Resident Inspector M. Kennard, Senior Operations Engineer W. Pursley, Health Physicist R. Reyes, Resident Inspector J. Rivera, Health Physicist J. Viera, Senior Operations Engineer

Approved By: David E. Dumbacher, Chief Reactor Projects Branch 3 Division of Reactor Projects

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Turkey Point Unit 3 & 4, 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

Debris and Unsecured Equipment in the RHR Pump Rooms Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.5] - Work 71152 Systems NCV 05000250,05000251/2021004-01 Management Open/Closed The NRC identified an adverse trend in the licensees ability to maintain the RHR pump rooms in compliance with housekeeping and conduct of maintenance procedures that prevent debris such as tie wraps, working gloves, pipe insulation, scaffold poles, tools, and uncontrolled and unsecured miscellaneous equipment from posing challenges to the screen and sump pump systems in the Unit 3 and Unit 4 RHR pump rooms. An NRC identified green non-cited violation (NCV) of Technical Specification 6.8.1 was identified for the licensees failure to implement required housekeeping and maintenance controls in the RHR pump rooms, as specified by procedures MA-AA-100-1008, Station Housekeeping and Material Control, and procedure MA-AA-100, Conduct of Maintenance.

PLANT STATUS

Unit 3 began the inspection period at 100 percent rated thermal power. The unit was down powered to zero percent power for a scheduled refueling outage on October 9, 2021. The unit was returned to rated thermal power on November 24, 2021, and remained at or near rated thermal power for the remainder of the inspection period.

Unit 4 operated at or near rated thermal power 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 activities described in IMC 2515, Appendix D, Plant Status, conducted routine reviews using IP 71152, Problem Identification and Resolution, 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.

REACTOR SAFETY

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the following systems:

Auxiliary Feedwater (AFW) pump room, on December 14, 2021 Unit 3 3A and 3B Emergency Diesel Generator (EDG) rooms, on December 23, 2021 Unit 4 4A and 4B EDG rooms, on December 23, 2021

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (3 Samples)

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

(1) Unit 3A and 3C Component Cooling Water (CCW) pumps; and 3A, 3B, and 3C CCW heat exchangers, while the 3A Residual Heat Removal pump (RHR), 3B CCW pump and the safety-related 3B 4kv bus were out of service (OOS) and Unit 3 was in single RHR train operation, on October 14, 2021.

(2) 3A, 4A, and 4B safety-related 4160-volt switchgears; 3A, 4A, and 4B High Head Safety Injection (HHSI) pumps, while the 3B HHSI pump and 3B safety-related 4160 switchgear was OOS, on October 25, 2021.

(3) Unit 3A, 3B, and Unit 4A HHSI pumps, Unit 3 and Unit 4 Refueling Water Storage Tanks (RSWT), and 3B RHR pump, while the 4B HHSI pump, 3A RHR pump and B AFW pumps were OOS, on November 10, 2021.

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

(1) The inspectors evaluated system configurations during a complete walkdown of the Unit 3 RHR system, on November 2-4, 2021.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (1 Sample)

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) Unit 3 and 4 Start-up transformer, Main transformer, and Auxiliary transformer areas, on October 13-14, 2021.

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

Main article: IP 71111.08

(1) The inspectors verified that the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation by reviewing the following activities from October 11-28, 2021:

1. Ultrasonic Examination a. 10"-SI-1301-17, Pipe to Elbow, ASME Class 1 (reviewed)b. 10"-SI-1301-18, Elbow to Elbow, ASME Class 1 (reviewed)c.

10"-SI-1301-20, Elbow to Elbow, ASME Class 1 (reviewed)d. 10"-SI-1301-21, Pipe to Branch Connection, ASME Class 1 (reviewed)e. 3-PCW-4, Head to Lower Shell, ASME Class 2 (reviewed)2. Visual Examination a. Bottom Mounted Instrument Nozzle Penetrations, PEN01, PEN12, PEN16, PEN27, PEN35, PEN38, PEN 46, and PEN50, ASME Class 1 (reviewed)3. Eddy Current Testing (ECT)a. SG 3A, tube R001C013, ASME Class 1 (observed)b. SG B, tube R004C077, ASME Class 1 (observed)

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)

(1) The licensee completed the annual requalification operating examinations 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 November 29, 2021, the inspector performed an in-office review of the overall pass/fail results of the individual operating examinations and the crew simulator operating examinations in accordance with Inspection Procedure (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 exam completed on November 29, 2021.

71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance

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

71111.11B - Licensed Operator Requalification Program and Licensed Operator

Performance

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

The inspectors completed an inspection to verify the licensees ability to evaluate the performance of their licensed operators during the conduct of examinations, to assess their ability to properly develop and administer requalification annual operating tests and biennial written examinations, to evaluate the performance of the control room simulator and their testing and maintenance of the simulator, to ensure that licensed individuals satisfy the conditions of their licenses, and to assess their effectiveness in ensuring that operator license conditions are satisfied.

(1) Biennial Requalification Written Examinations

The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered on September 23, 2021

Annual Requalification Operating Tests

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

Administration of an Annual Requalification Operating Test

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

Requalification Examination Security

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

Remedial Training and Re-examinations

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

Operator License Conditions

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

Control Room Simulator

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

Problem Identification and Resolution

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

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)

(1) The inspectors observed and evaluated licensed operator performance in the Control Room during Unit 3 reactor physics tests and start-up through MODE 2 and criticality on November 19, 2021.

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

(1) The inspectors observed and evaluated Just-In-Time training in the simulator for a down-power and unit manual trip for the upcoming refueling outage administered to an operating crew on October 1, 2021.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (2 Samples)

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

(1) Maintenance Rule Functional Failure (MRFF) AR 2358251 - Degraded Cables at Location Manhole 320 and AR 2397255 - MRFF for Manholes 306 and 320, Due to Failure to Maintain Structural Integrity

(2) AR 02377877, HAS-016A Train A Post Accident Hydrogen Monitor South Bottle Isolation Valve is Leaking Oxygen

Aging Management (IP Section 03.03) (1 Sample)

The inspectors evaluated the effectiveness of the aging management program for the following SSCs that did not meet their inspection or test acceptance criteria:

(1) Degraded coatings and rust on containment liner: CR 02408675 (39 level),

===02408750 (58 level), 02408244 (14 level), and 02407783 (moisture barrier)

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01)===

Main article: IP 02408

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 3 shutdown risk assessment during Mode 6 yellow risk profile, due to the reactor coolant system (RCS) drained below the flange for reactor head removal, and Unit 4 online risk assessment while operating at full rated power, on October 13, 2021.

(2) Unit 3 shutdown risk assessment during defueled yellow risk profile due the RCS drained down to hot leg mid-nozzle, the 3B safety-related 4160-volt switchgear and the 3A EDG OOS; Unit 4 online risk assessment with the containment radiation monitors R-11/12 OOS, on October 21, 2021.

(3) Unit 3 shutdown risk assessment during defueled yellow risk profile due to the 3B safety-related 4160-volt switchgear OOS, and Unit 4 online risk assessment while operating at full rated power with the 3B HHSI pump unavailable, on October 25, 2021.

(4) Unit 3 shutdown risk assessment while in MODE 5 and Unit 4 online risk assessment while operating a full rated power with the 3A RHR, 4B HHSI pump, B AFW pump, and the unit 4 pressurizer power operated relief valve block valve OOS, on November 10, 2021.

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)

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

(1) AR 02408108, Unit 3 3A RHR Pump Seal has Leakage

(2) AR 02408714, MOV-3-863 Test Acceptance Criteria Not Met

(3) AR 02409956, 3A EDG Coolant Return Coupling Leak

(4) AR 02411149, Identified 3" Long Boric Acid Accumulation Below the Canopy Seal Weld on Control Rod Drive Mechanism (CRDM) 15

(5) AR 02411150, Identified Boric Acid Leak on Core Exit Thermocouple (CET) 57; AR 02411154, Identified Boric Acid Leakage at Swage Lock Fitting on CET 51

(6) AR 02411240, Identified Boric Acid Residue on the Reactor Vessel Stud Insulation Package

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)

The inspectors evaluated the following temporary or permanent modifications:

(1) EC 296594, U4 Containment Impressed Current Cathodic Protection (ICCP)

Discontinuity

(2) EC 296989, Abandonment of CET TE-3-39E (H-9) and TE-3-49E (N-8)

71111.19 - Post-Maintenance Testing

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

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

(1) WO 40795920, 40724574, and 40724651, Post Maintenance Tests for Seal Replacement using surveillance procedure 3-OSP-050.2C, Residual Heat Removal Train A Comprehensive Test - Cooldown Alignment, on October 30, 2021.

(2) WO 40785630, 40789708 Post Maintenance Tests for Cable 3AB06/3AB06-3C03/002, on November 8, 2021.

(3) WO 40785630, 40789708 Post Maintenance Tests for Cable 3AB01/3AB01-3B06/001, on November 9, 2021.

(4) WO 40151537 and 40151538, Post Maintenance Tests for Containment Spray Piping Modification EC 291279, on November 5, 2021.

(5) WO 4067079701, 4067079702 and 4067079703, Replace positioner and perform calibration of actuator on air operated valve CV-3-2816, steam generator Train 1 AFW control valve, and test per MA-AA-100-1013, Air Operated Valve Diagnostic Testing and Inspection; and 3-OSP-075.10, AFW Flow Control Valve Operability Test, on November 11, 2021.

(6) WO 4080235802 and 4080235202, NOP/NOT post maintenance leak tests on CET-51 and CET-57, after repairing through-wall leak and swage lock fitting boron leaks and abandoning the CETs by cutting and caping tubes using swage lock fittings, on November 19, 2021.

71111.20 - Refueling and Other Outage Activities

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

(1) The inspectors evaluated PT3-32 activities from October 8-November 22, 2021.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

Main article: IP 71111.22

(1) 3-OSP-072.6, Main Steam Safety Valve Setpoint Surveillance Using Team Trevistest Mark Viii Equipment, (for relief valves RV-3-1400, RV-3-1401, RV-3-1402, and RV-3-1407), on October 8, 2021.

(2) 3-OSP-203.1, Train A Engineered Safeguards Integrated Test, completed November 1-9, 2021.

(3) 3-OSP-023.1, 3B EDG Normal Start Test, on November 29, 2021.

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

(1) 3-OSP-051.5, Local Leak Rate Tests (Penetration 53 - PAC Vent), on October 21,

RADIATION SAFETY

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 how the licensee instructs workers on plant-related radiological hazards and the radiation protection requirements intended to protect workers from those hazards.

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) workers exiting the RCA during Unit 3 refueling outage

(2) licensee surveys of potentially contaminated material leaving the RCA

(3) workers exiting Unit 3 containment during Unit 3 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) RWP No. 21-3100, Refueling Activities, Rev. 1

(2) RWP No. 21-3105, CET Replacement, Rev. 2

(3) RWP No. 21-3002, Radiation Protection Outage Containment Activities (Bulk Work),

Rev. 0 High Radiation Area and Very High Radiation Area Controls (IP Section 03.05) (5 Samples)

The inspectors evaluated licensee controls of the following High Radiation Areas and Very High Radiation Areas:

(1) Radwaste Building High Level Storage Area (LHRA)

(2) Auxiliary Building Unit 4 Base and Cation Room (LHRA)

(3) Auxiliary Building Basement (LHRA)

(4) Radwaste Building South Filling Room (LHRA)

(5) Unit 3 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.

71124.02 - Occupational ALARA Planning and Controls

Radiological Work Planning (IP Section 03.01) (4 Samples)

The inspectors evaluated the licensees radiological work planning by reviewing the following ALARA plans.

(1) ALARA Plan U3R32 Core Exit Thermocouple Replacement

(2) ALARA Plan U3R32 Secondary Side Steam Generator Work

(3) ALARA Plan U3R32 Cont. Spray Pipe Replacement

(4) ALARA Plan U3R32 Reactor Sump Work-Non-Legacy Boric Acid

Verification of Dose Estimates and Exposure Tracking Systems (IP Section 03.02) (5 Samples)

The inspectors reviewed the following as low as reasonably achievable planning documents:

(1) ALARA Plan U3R32 Reactor Sump Work-Non-Legacy Boric Acid

(2) ALARA Plan U3R32 Secondary Side Steam Generator Work

(3) ALARA Plan U3R32 Core Exit Thermocouple Replacement

Additionally, the inspectors reviewed the following radiological outcome evaluations:

(4) U4R32 Refueling Activities, Including Fuel Cleaning and All Support Work Outage Critique

(5) U4R32 Reactor Sump Work-Non-Legacy Boric Acid Post Job Review

Implementation of ALARA and Radiological Work Controls (IP Section 03.03) (3 Samples)

The inspectors reviewed as low as reasonably achievable practices and radiological work controls including:

(1) RWP 21-3024, Bottom Mounted Instrumentation Project (BMI) including MIMS Troubleshoot and Repair Work

(2) RWP 21-3020, Unit 3R32 Steam Generator Secondary Side Work, Including All Support Work

(3) RWP 21-3105, Core Exit Thermocouple Replacement

Radiation Worker Performance (IP Section 03.04) (1 Sample)

(1) RWP 21-3100 and 21-3024, which included Unit 3 reactor reassembly, reactor head set, reactor cavity drain down, Tri-Nuke filter removal, under vessel inspection activities, upper internals move and general work in the reactor cavity

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 Emergency Ventilation System

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

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

(1) Portable HEPA Unit No. 022

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's external dosimetry program.

Internal Dosimetry (IP Section 03.03) (1 Sample)

The inspectors evaluated the following internal dose assessments:

(1) The inspectors reviewed the following:

Whole Body Counts Condition Report 20352998 and results of in-vivo analysis performed on April 16, 2020 Condition Report 20370956 and results of two in-vivo analyses performed on October 10, 2020

In-Vitro Internal Monitoring Licensee performed no In-Vitro analysis during the period covered by the inspection.

Dose Assessments Performed Using Air Sampling and Derived Air Concentration-Hour Monitoring Licensee did not perform any DAC-Hr assignments during the period covered by the inspection.

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

The inspectors evaluated the following special dosimetric situations:

(1) Licensees implementation of requirements to manage radiation protection of declared pregnant workers for two workers

(2) Licensee calculations of EDEX from multi-dosimetry results for RWP 20-3100, Unit 3 Reactor Head Set, April 14, 2020

(3) Licensees application of multibadging requirements to determine EDEX for workers on RWP 21-3100, Unit 3 Reactor Head Set, November 3, 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) Telepole in calibration lab

(2) AMP-100 in calibration lab

(3) Ludlum 9-3 in calibration lab

(4) RadEye-G in calibration lab

(5) Cronos at RCA exit

(6) ARGOS at RCA exit

(7) GEM-5 at PA exit

(8) Control Room ARM

(9) Unit 3 SFP ARM

Calibration and Testing Program (IP Section 03.02) (13 Samples)

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

(1) MGP Instruments Telepole WR, SN #6601-090

(2) Canberra/Mirion Model 2250 Fastscan 2 - Whole Body Counter, SN #13000003

(3) Canberra/Mirion Model 2250 Fastscan 2 - Whole Body Counter, SN #97-7040

(4) Unit 3 - Containment High-Range Radiation Monitor, RAD-3-6311A

(5) Unit 3 - Containment High-Range Radiation Monitor, RAD-3-6311B

(6) Unit 4 - Containment High-Range Radiation Monitor, RAD-3-6311A

(7) Unit 4 - Containment High-Range Radiation Monitor, RAD-3-6311B

(8) Mirion AMP-200, GM Tube-Based Ratemeter and Area Monitor, SN #7705-020

(9) Canberra ARGOS 5AB, SN #0904-108

(10) Cronos Gamma Object/Tool Monitor, SN #1394

(11) GEM-5, Gamma Exit Monitor, SN: 1212-220

(12) Ludlum Model 9-3, Ion Chamber Survey Meter, SN #322843

(13) Thermo-Scientific Model RadEye G, SN #30042

Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (3 Samples)

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

(1) Unit 3 - Spent Fuel Pool Vent Stack Radiation Monitor (RAD-3-6418 [SPING])

Calibration, dated May 20, 2020

(2) R-18 Liquid Effluent Process Radiation Monitor Calibration dated, July 6, 2021

(3) R-18 Liquid Effluent Process Radiation Monitor Calibration dated, January 8,

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)===

Main article: IP 71151