Text

Reissue - Surry Power Station - Integrated Inspection Report 05000280/2022004 and 05000281/2022004
	ML23243A906
Person / Time
Site:	Surry
Issue date:	09/01/2023
From:	Matthew Fannon; Division Reactor Projects II
To:	Carr E; Virginia Electric & Power Co (VEPCO)
Shared Package
ML23243A907	List: IR 05000280/2022004;
References
	EA-22-084 IR 2022004
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SUBJECT:

REISSUE - SURRY POWER STATION - INTEGRATED INSPECTION REPORT 05000280/2022004 AND 05000281/2022004

Dear Eric S. Carr:

The U.S. Nuclear Regulatory Commission (NRC) identified the need to reissue NRC Inspection Report 05000280/2022004 and 05000281/2022004, dated February 13, 2023 (ADAMS Accession Number ML23041A023). Specifically, a minor violation associated with Licensee Event Report (LER) 05000280,05000281/2022-001-00, was omitted from the inspection report.

The Inspection Results section has been revised to include this minor violation. As a result, the NRC has reissued the report in its entirety.

On December 31, 2022, the NRC completed an inspection at Surry Power Station. On January 19, 2023, the NRC inspectors discussed the results of this inspection with James Shell, Director, Nuclear Station Safety and Licensing, and other members of your staff. The results of this inspection are documented in the enclosed report.

Three findings of very low safety significance (Green) are documented in this report. Three of these findings involved violations of NRC requirements. We are treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2 of the Enforcement Policy.

Licensee-identified violations which were determined to be of very low safety significance and Severity Level IV are documented in this report. We are treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violations or the significance or severity of the violations 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 Surry Power Station.September 1, 2023 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 Surry Power Station.

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, Matthew S. Fannon, Chief Reactor Projects Branch 4 Division of Reactor Projects Docket Nos. 05000280 and 05000281 License Nos. DPR-32 and DPR-37

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000280 and 05000281

License Numbers: DPR-32 and DPR-37

Report Numbers: 05000280/2022004 and 05000281/2022004

Enterprise Identifier: I-2022-004-0023

Licensee: Virginia Electric and Power Company

Facility: Surry Power Station

Location: Surry, VA

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

Inspectors: S. Kennedy, Senior Resident Inspector E. Bousquet, Resident Inspector J. Diaz-Velez, Senior Health Physicist S. Downey, Senior Reactor Inspector B. Kellner, Senior Health Physicist J. Reed, Health Physicist J. Rivera, Health Physicist A. Rosebrook, Senior Reactor Analyst M. Schwieg, Senior Reactor Inspector B. Towne, Senior Resident Inspector A. Wilson, Senior Project Engineer

Approved By: Matthew S. Fannon, Chief Reactor Projects Branch 4 Division of Reactor Projects

Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Surry Power 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. A licensee-identified non-cited violation is documented in report section: 7115

List of Findings and Violations

Transient Combustible Stored in a Restricted Area Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [P.5] - 71111.05 Systems NCV 05000280/2022004-01 Operating Open/Closed Experience An NRC identified finding of very-low safety significance (Green) and an associated Non-Cited Violation (NCV) of License Condition 3.I, "Fire Protection," associated with the licensee's failure to implement and maintain in effect, the provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report (UFSAR), which resulted in storage of a transient combustible within a restricted or combustion free zone.

Failure to Manage Risk During "C" Reserve Station Service Transformer Maintenance Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [H.13] - 71111.13 Systems NCV 05000280,05000281/2022004-02 Consistent Open/Closed Process An NRC-identified finding of very low safety significance (Green) and an associated Non-Cited Violation of 10CFR50.65(a)(4), "Requirements for monitoring the effectiveness of maintenance at nuclear power plants, was identified for the failure of the licensee to manage the increase in risk during C reserve station service transformer (RSST) maintenance.

Specifically, the licensee did not include the emergency diesel generator (EDG) output breakers in the protected equipment boundary for the C RSST work activity, which resulted in the EDGs not being fully protected.

Inadequate Cause Evaluation for #1 EDG Failure Cornerstone Significance Cross-Cutting Report Aspect Section Mitigating Green [P.2] - 71153 Systems NCV 05000281,05000280/2022004-03 Evaluation Open/Closed An NRC identified finding of very low safety significance (Green) and an associated Non-Cited Violation (NCV) of 10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, for the failure to implement licensee procedure PI-AA-300, Cause Evaluation.

Specifically, during the extent of condition review, the licensee did not identify that safety-related motors are similar objects that could be affected by the same cause of the #1 emergency diesel generator failure which occurred on July 18, 2022, and bounded the condition to only the stations diesel generators.

Appendix R Cable Separation Non-Compliance Cornerstone Severity Cross-Cutting Report Aspect Section Not Applicable Severity Level IV Not Applicable 71153 NCV 05000280,05000281/2022004-04 Open/Closed EA-22-084 The licensee identified a non-compliance with the regulatory criteria set forth in 10 CFR 50,

Appendix R,Section III.G. Specifically, control power cables associated with emergency diesel generation output breakers and emergency bus feeder breakers were identified to not meet the requirements of 10 CFR 50, Appendix G, Section III.G 2, following review of Fleet Operating Experience at the North Anna Power Station. There was no performance deficiency identified as the condition had been addressed in the Appendix R compliance report using the circuit analysis available at the time.

Additional Tracking Items

Type Issue Number Title Report Section Status URI 05000280,05000281/20 Appendix R Cable 71153 Closed 22003-03 Separation LER 05000280,05000281/20 LER 2022-001-00 for Surry 71153 Closed 22-001-00 Power Station, Unit 1 and Unit 2, Failure of Two Intake Canal Level Probes Due to Biofouling LER 05000280,05000281/20 LER 2022-002-00 for Surry 71153 Closed 22-002-00 Power Station, Units 1 and 2, Failure of Unit 1 Emergency Diesel Generator Results in an Operation or Condition Prohibited by Technical Specifications

PLANT STATUS

Unit 1 began the inspection period at or near rated thermal power (RTP). On October 30, the unit was shut down for a planned refueling outage. The unit was returned to RTP on December 19 and remained at or near RTP for the remainder of the inspection period.

Unit 2 operated at or near RTP 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, 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

71111.04 - 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) Alternate AC diesel during the # 2 EDG out of service for monthly performance test on October 17, 2022

(2) Unit 1 safety systems (low head safety injection, inside recirculation spray, outside recirculation spray, containment spray, and auxiliary feedwater) during transition from hot shutdown to cold shutdown on October 30, 2022

(3) Spent fuel pit cooling following Unit 1 core offload for refueling on November 11, 2022

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

(1) The inspectors evaluated system configurations during a complete walkdown of the residual heat removal system in the shutdown cooling mode of operation on November 1, 2022.

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:

(1) Fire pump house, fire areas 32A and 32B, on October 6, 2022

(2) Emergency diesel generator room 1, fire area 6, on October 14, 2022

(3) Unit 1 cable vaults and tunnels, fire zone 1, on October 21, 2022

(4) Unit 1 containment, fire area 15, on November 3, 2022

71111.06 - Flood Protection Measures

Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)

The inspectors evaluated internal flooding mitigation protections in the:

(1) Mechanical equipment room 5 on November 17, 2022

===71111.08P - Inservice Inspection (ISI) Activities (PWR)

PWR Inservice Inspection Activities Sample (IP Section 03.01)===

Main article: IP 71111.08

(1) The inspectors reviewed the following In-service activities from November 14, 2022 to November 21, 2022:

03.01.a - Nondestructive Examination and Welding Activities Ultrasonic examinations on vessel shell welds Visual examinations of the core barrel and thermal shield Visual examinations for reactor coolant system (RCS) leakage (VT-2)

Liquid penetrant examination for 10 residual heat removal system (RHR)piping and valve 1-RH-20 Welding activities on new 10 RHR piping and valve 1-RH-20

03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities Boric acid program corrective action reports

03.01.d - Pressurized-Water Reactor Steam Generator (SG) Tube Examination Activities SG 1A - R1C86 SG 1B - R45C48, R40C51 SG 1C - R39C23

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 7, 2022, 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 March 31, 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 main control room during the Unit 1 shutdown for a refueling outage on October 29, 2022.

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

(1) The inspectors observed and evaluated licensed operator requalification training involving a scenario which included a reactor coolant system leak from the residual heat removal system suction, followed by a loss of all AC power on October 18, 2022.

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) 1-EP-BKR-14J4, 1-RS-P-1B inside recirculation spray pump breaker, failed to close during logic test on November 1, 2022.

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) Unit 1 auxiliary feedwater full-flow recirculation piping excavation extent of condition evaluation as a result of Unit 2 auxiliary feedwater full-flow recirculation line leaks on December 2, 2022.

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (4 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) Emergent risk assessment on Units 1 and 2 during "B" main control room chiller inoperable on October 20, 2022

(2) Unit 1 shutdown risk plan review in preparation for 1R31 outage on October 31, 2022

(3) Risk mitigation actions for Unit 1 residual heat removal system following entry into cold shutdown on November 1, 2022

(4) Risk mitigation actions for U1 electrical configuration with "C" reserve service station transformer in backfeed on November 3, 2022.

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)

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

(1) Condition report (CR) 1210757, "B" main control room chiller (1-VS-E-4B) thermal expansion valves found non-responsive resulting in 1-VS-E-4B being declared inoperable on October 19, 2022

(2) CR1211518, N-32 (Unit 1 source range nuclear instrument channel 2) declared inoperable on October 29, 2022

(3) CR1212472, Unit 1 charging pump suction valves (1-CH-MOV-1115B/D) found closed, affecting cross-tie availability on November 10, 2022

(4) CR1213925, Unit 2 computer enhanced rod position indication system inoperable on November 28, 2022

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) Design equivalent change package SU-22-00161 for 1-SI-TV-101B, Unit 1 accumulator vent outside trip valve, seat modification

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (9 Samples)

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

(1) 1-OSP-SI-012, Leakage Test of Low Head Safety Injection (LHSI) Suction MOV for post maintenance testing of 1-SI-MOV-1826B (LHSI pump "B" suction from refueling water storage tank) on October 12, 2022

(2) 1-OPT-SI-005, LHSI Pump Test to satisfy post-maintenance test for return to service of 1-SI-P-1B following maintenance on October 12, 2022

(3) 2-OPT-CH-005, Boric Acid Transfer Pumps Operability and Performance Test for post maintenance testing of 2D boric acid transfer pump on October 31, 2022

(4) Return to service testing of N32 source range nuclear instrument following replacement on November 3, 2022 (Work Order 38204304661)

(5) 0-ECM-0102-02, Stationary Battery Intercell Connections Cleaning and Lubrication, following maintenance to address high resistance readings between cells 28 and 29 of the 1B station battery, on November 15, 2022

(6) 1-OSP-FW-001, Auxiliary Feedwater Turbine Overspeed Trip Test, following inspection of overspeed trip device on December 2, 2022

(7) 0-ECM-0103-02, Electrical Corrective Maintenance, following maintenance on the 1B-1 battery charger panel on December 2, 2022

(8) 1-OPT-CT-206, Leak Test of 1-RS-E-1D Service Water Side, following weld repair on D recirculation spray heat exchanger service water discharge piping on December 6, 2022

(9) 0-OPT-ZZ-008, American Society of Mechanical engineers (ASME) System Pressure Tests, following weld repair of the Unit 1 charging pump intermediate seal cooler on December 7, 2022

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 October 30, 2022, to December 13, 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) 0-EPT-0104-01, Semi-annual Station Battery Test, on October 19, 2022

(2) 2-OPT-FW-003/007, Turbine-driven Auxiliary Feedwater (AFW) Pump 2-FW-P-2/Turbine Driven AFW Pump Steam Supply Line Check Valve Test, on October 25, 2022

RCS Leakage Detection Testing (IP Section 03.01) (1 Sample)

(1) 1-OPT-RC-10.1, Reactor Coolant Leakage Walkdown at Cold Shutdown, on November 1, 2022

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

(1) 1-OPT-CT-201, Containment Isolation Valve Local Leak Rate Testing (Type C Containment Testing) on December 12, 2022

FLEX Testing (IP Section 03.02) (1 Sample)

(1) 0-MPM-1960-01, Semi-Annual or Annual Test of Beyond Design Basis (BDB) FLEX Equipment, BDB Auxiliary Feedwater Pump 2B on November 3,

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 radiologically controlled area (RCA) during routine operations and Unit 1 refueling outage.

(2) Observed radiation protection (RP) staff surveying and releasing personal items leaving the RCA

(3) Observed licensee controls for highly activated or contaminated materials (non-fuel)stored in spent fuel pool

Radiological Hazards Control and Work Coverage (IP Section 03.04) (5 Samples)

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

(1) RWP 2515-1, MRP 227 ISI Inspection Phase 2 Activities

(2) RWP 2551, SLR - CAT Elimination Project Activities

(3) RWP 2516, Lower Internals Lift & Set Activities

(4) RWP 2501 "B" Loop S/G Primary Eddy Current Activities

(5) RWP 2104, Mechanical Maintenance Support 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:

(1) OVHD gas surge tank room

(2) Units 1/2 volume control tank room

(3) Auxiliary building sump

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) Main control room ventilation system

(2) Safeguards area exhaust filtration system

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

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

(1) High-efficiency particle absorbing (HEPA) Unit HV-1600-02, used on "A" Loop 11/12/2022

(2) HEPA Unit HV-1600-04, used on "B" Loop 11/12/2022

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.

Special Dosimetric Situations (IP Section 03.04) (1 Sample)

The inspectors evaluated the following special dosimetric situations:

(1) Declared pregnant worker.

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 auxiliary building

(2) Portable friskers located at multiple areas within the auxiliary building

(3) Portable ion chambers survey instruments (RO-20) located at the instrument issue area

(4) Portable Geiger-Muller (GM) survey instruments (Radeye G) located at the instrument issue area

(5) Portable telescoping GM survey instruments (Telepole & Telepole II) located at the instrument issue area

(6) Argos-5APB/Zeus personnel contamination monitors located at the RCA exit

(7) GEM-5APB portal monitors located at the primary access point exit

(8) Sirius hand and foot monitors located outside the containment step off pad and at exit points to the yard

(9) Liquid radioactive waste radiation monitor (1-RE-131) located in the Surry radwaste facility (initiates discharge isolation on alarm)

(10) Radwaste facility vent stack radiation monitor (RE-100/101)

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

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

(1) Work Order (WO) 38204200713, Calibrate 1-RM-RMS~157 (Main Control Room Area Radiation Monitor)

(2) WO 38204219098, Containment High Range Radiation Monitor 2-RM-RMS-228 Channel Calibration, 11/11/2021

(3) WO 38204218983, Containment High Range Radiation Monitor 2-RM-RMS-227 Channel Calibration, 11/11/2021

(4) Eberline RO-20 ion chamber dose rate instrument, serial number (S/N) 12251, calibration dates 3/23/2021 and 5/2/2022

(5) MGP AMP-100 underwater GM tube dose rate instrument, S/N 5012-044, calibration dates 9/28/2017 and 8/18/2022

(6) MGP Telepole GM tube dose rate instrument, S/N 6609-081, calibration dates 11/4/2021 and 7/7/2022

(7) Mirion Telepole II GM tube dose rate instrument, S/N 232920-133, calibration dates 5/11/2021 and 11/6/2021

(8) Eberline RO-20 ion chamber dose rate instrument, S/N 12074, calibration dates 7/14/2021 and 6/13/2022

(9) Thermo Radeye G GM tube dose rate instrument, S/N 30273, calibration dates 11/20/2019 and 2/24/2022

(10) Model CMP-0523-CV Portable air sampler, S/N 21059, calibration dates 8/27/2021 and 8/1/2022

(11) Argos-5PAB/Zeus personnel contamination monitor, S/N 1112-247, calibration dates 7/29/2021 and 4/19/2022

(12) Cronos 4 tool/equipment monitor, S/N 1312-346, calibration dates 4/20/2021 and 4/13/2022

(13) GEM-5 gamma portal monitor, S/N 1604-047, calibration dates 6/14/2021 and 6/27/2022

(14) Thermo Radeye GX frisker, S/N 11248, calibration dates 10/20/2020 and 10/18/2021

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) WO 38204220513, 1-VG-RM-131 Calibration (Vent Stack No. 2 Normal and High Range Effluent Radiation Monitor), 10/05/2021

(2) WO 38204216269, Calibrate Unit 2 Containment Particulate and Gaseous radiation Monitor (2-RM-RMS 259/260), 10/21/2021

(3) WO 38204202626, Calibrate Unit 1 Containment Particulate and Gaseous Radiation Monitor (1-RM-RMS 159/160), 03/22/2021

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)===

Main article: IP 71151

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