IR 05000334/2023002

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Integrated Inspection Report 05000334/2023002 and 05000412/2023002
ML23221A024
Person / Time
Site: Beaver Valley  FirstEnergy icon.png
Issue date: 08/09/2023
From: Matt Young
NRC/RGN-I/DORS
To: Blair B
Energy Harbor Nuclear Corp
References
IR 2023002
Download: ML23221A024 (1)
v • d • e


Text

August 9, 2023

SUBJECT:

BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000334/2023002 AND 05000412/2023002

Dear Barry Blair:

On June 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Beaver Valley Power Station, Units 1 and 2. On July 19, 2023, the NRC inspectors discussed the results of this inspection with you 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, Digitally signed by Matthew R. Matthew R. Young Date: 2023.08.09 Young 08:31:46 -04'00'

Matt R. Young, Chief Projects Branch 2 Division of Operating Reactor Safety Docket Nos. 05000334 and 05000412 License Nos. DPR-66 and NPF-73

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000334 and 05000412 License Numbers: DPR-66 and NPF-73 Report Numbers: 05000334/2023002 and 05000412/2023002 Enterprise Identifier: I-2023-002-0027 Licensee: Energy Harbor Nuclear Corporation Facility: Beaver Valley Power Station, Units 1 and 2 Location: Shippingport, PA Inspection Dates: April 1, 2023 to June 30, 2023 Inspectors: N. Day, Senior Resident Inspector J. DeBoer, Senior Project Engineer B. Edwards, Senior Health Physicist R. Rolph, Resident Inspector B. Towne, Resident Inspector A. Turilin, Reactor Inspector Approved By: Matt R. Young, Chief Projects Branch 2 Division of Operating Reactor Safety Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Beaver Valley Power Station, Units 1 and 2, 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 operated at or near rated thermal power for the entire inspection period.

Unit 2 began the inspection period at rated thermal power. On April 7, 2023, the unit was shutdown for a planned refueling outage. On May 26, 2023, following the refueling outage, the unit returned to rated thermal power. On June 2, 2023, the licensee reduced power to 81 percent to repair a leak on the heater drain system. On June 3, 2023, the unit returned to full power and remained at or near rated thermal power for the remainder of the 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

71111.01 - Adverse Weather Protection

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

(1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal hot temperatures and seasonal heavy rain/thunderstorms on June 2, 2023.

71111.04 - Equipment Alignment

Partial Walkdown (IP Section 03.01) (4 Samples)

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

(1) Unit 2, recirculation spray system train 'B' during operation at power in standby mode, April 6, 2023
(2) Unit 2, spent fuel pool cooling system following core offload, April 18, 2023
(3) Unit 2, component cooling water train 'B' while 'A' and 'C' component cooling heat exchangers are out of service, April 24, 2023
(4) Unit 1, auxiliary feedwater train 'B' while surveillance being ran on the train 'A,'

May 15, 2023 Complete Walkdown (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 residual heat removal system during decay heat removal following shutdown to Mode 5 on April 12, 2023.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection (IP Section 03.01) (5 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) Unit 1, safeguards building, elevation 735', fire area 1 PFP-SFGB-735-AUX, April 5, 2023
(2) Unit 2, turbine building, 774', 752', and 730' east and west, fire compartment 2-TB-1, April 11, 2023
(3) Unit 2, containment building, elevation 767', 738', and 692', fire compartment 2-RC-1, April 12, 2023
(4) Unit 2, auxiliary boiler 730' and 755' elevations, fire areas 2PFP-ABBX-730 and 2PFP-ABBX-755, May 4, 2023
(5) Unit 1, diesel generator 2 room, elevation 735', fire compartment 1-DG-2, May 30, 2023

71111.06 - Flood Protection Measures

Flooding (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated Units 1 and 2 flooding mitigation protections in the intake building on June 14, 2023.

71111.07A - Heat Exchanger/Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1) Unit 2, No. 2 emergency diesel generator jacket water heat exchanger, 2EGS-E22B

===71111.08P - Inservice Inspection Activities (PWR) The inspectors verified that the reactor coolant system boundary, reactor vessel internals, risk significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from April 17 to April 27, 2023.

PWR Inservice Inspection Activities - Nondestructive Examination (NDE) and Welding Activities (IP Section 03.01) ===

Main article: IP 71111.08

The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:

(1) Eddy Current Examination
  • Automated eddy current test of the RPV head, vent line ID post repair axial scan (NDE Report DMW-R23-VL01-AXIAL-POSTREPAIR-01)
  • Automated eddy current test of the RPV head, vent line ID post repair circ scan (NDE Report DMW-R23-VL01-CIRC-POSTREPAIR-01)
(2) Dye Penetrant Examination
  • Manual dye penetrant test of the RPV head, BV Unit 2 Rx head vent Line - Final (NDE Report NDE-919522-008)
  • Manual dye penetrant test of the RPV head, BV Unit 2 Rx head vent Line - Final, After Buffing (NDE Report NDE-919522-007)
  • Manual dye penetrant test of the RPV head, BV Unit 2 Rx head vent Line - Final, After Buffing (NDE Report NDE-919522-006)
  • Manual dye penetrant test of the RPV head, BV Unit 2 Rx head vent Line - BV Unit 2 Rx Head Vent Line - After Weld Layer #4 (NDE Report NDE-919522-005)
  • Manual dye penetrant test of the RPV head, BV Unit 2 Rx head vent Line - BV Unit 2 Rx Head Vent Line - After Weld Layer #3 (NDE Report NDE-919522-004)
  • Manual dye penetrant test of the RPV head, BV Unit 2 Rx head vent Line - BV Unit 2 Rx Head Vent Line - After Weld Layer #2 (NDE Report NDE-919522-003)
  • Manual dye penetrant test of the RPV head, BV Unit 2 Rx head vent Line - First Layer (NDE Report NDE-919522-002)
  • Manual dye penetrant test of the RPV head, BV Unit 2 Rx head vent Line - Seal Weld, Base Material, Vent Tube (NDE Report NDE-919522-001)
  • Manual dye penetrant test of RPV head, BV Unit 2 Rx head control rod drive mechanism penetrations 28, 37, 40, 44 and vent line Jweld (NDE Reports WDI-PJF-349493-FSR-001))
(3) Ultrasonic Examination
  • Manual ultrasonic testing of safety injection system pipe to pipe weld, 2SIS-012-1A (NDE Report UT-23-1024)
(4) Ultrasonic Examination
  • Automated ultrasonic testing of outlet nozzle at 265 to safe-end dissimilar metal butt weld, 2RCS*REV21-N-24 (NDE Report WDI-PJF-348865-FSR-001)
(5) Welding Activities
  • Machine gas tungsten arc weld process to apply ambient temperature temperbead overlay
  • Reactor cooling system, component ID 2RCS-REV21, welding activities associated with the repair of the reactor vessel head at the reactor vessel level instrumentation system penetration under WO 200913374. The post-welding NDE included eddy current testing (NDE Reports DMW-R23-VL01-AXIAL-POSTREPAIR-01 and DMW-R23-VL01-CIRC-POSTREPAIR-01) and die penetrant testing (NDE Reports: NDE-919522-001 through 919522-008)

PWR Inservice Inspection Activities - Vessel Upper Head Penetration Inspection Activities (IP Section 03.02) (1 Sample)

The inspectors verified that the license conducted the following vessel upper head penetration inspections and addressed any identified defects appropriately:

(1) Ultrasonic testing of reactor vessel head control rod drive mechanism nozzle penetrations J-welds 16, 27, 28, 40 (NDE Reports DMW-2R23-OH01-16-01R, DMW-

2R23 -CP04-27-01Y, DMW-R23-CP04-28-02G, DMW-2R23-CP04-40-01Y, 02Y)

PWR Inservice Inspection Activities - Boric Acid Corrosion Control Inspection Activities (IP Section 03.03) (1 Sample)

The inspectors verified the licensee is managing the boric acid corrosion control program through a review of the following evaluations:

(1)

  • CR-2023-02878, for the 2SIS-131 low-head safety injection pump discharge to loops 21B, 'C' hot leg vent Swagelok threaded test connection of the safety injections system
  • CR-2023-03024, for the 2CHS-LCV115D charging pump suctions from refueling water storage tank valve packing of the chemical and volume control system

The inspectors verified that the licensee is monitoring the steam generator tube integrity appropriately through a review of the following examinations:

(1)

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 Unit 2 operations' personnel during power reduction and unit shutdown to Mode 5 for the 2R23 refueling outage on April 8, 2023.

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

(1) The inspectors observed a Unit 1 simulator evaluation that included hot weather events based on operational experience on June 2, 2023.

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (3 Samples)

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

(1) Unit 1, condenser hotwell level controller, LC-1CN-102, failed causing LCB-1CN-102 and LCV-1CN-103 to open during 100 percent power operation, resulting in a decrease in steam generator level due to the decrease in main feed pump suction head caused by condensate being diverted to the condenser, March 13, 2023
(2) Unit 2, pressurizer power operated relief valve, 2RCS-PCV455C, failed to indicate properly during performance of 2OST-6.8, April 11, 2023
(3) Unit 2, turbine driven auxiliary feedwater pump steam inlet solenoid, May 15, 2023

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management (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) Unit 2, inspectors evaluated elevated overall plant risk for scheduled maintenance and refueling activities during refueling outage 2R23, April 4, 2023
(2) Unit 2, motor control cabinet (MCC) 2-E05, outage resulting in an unplanned Yellow risk condition for containment key safety function during fuel movement, April 24, 2023
(3) Unit 2, Yellow risk when entering reduced inventory during repair of leak on core exit thermocouple nozzle assembly, May 17, 2023
(4) Units 1 and 2, elevated risk during the No. 2 138kV bus removal to support internal inspections of breakers and disconnects of PCB-85 and PCB-83, June 6, 2023

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (7 Samples)

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

(1) Unit 2, N31 source range nuclear instrument due to indicating zero counts after being energized during plant shutdown, April 8, 2023
(2) Unit 2, pressurizer power operated relief valve due to failure to indicate during performance of 2OST-6.8, April 11, 2023
(3) Unit 2, No. 2 emergency diesel generator follow-up operability determination due to the engine driven fuel oil pump shaft sheared, April 22, 2023
(4) Unit 2, residual heat removal system train 'B' heat exchanger bypass flow control valve, 2RHS-FCV-605B, failed to stroke during 2OM-10.4.B, May 12, 2023
(5) Unit 2, turbine driven auxiliary feedwater pump operability determination following steam leak from welded connection of 2MSS-SOV105B turbine steam inlet valve, May 15, 2023
(6) Unit 2, emergency diesel generator No. 2 operability determination due to blown control power fuse in MCC-2-E07-1D, May 30, 2023
(7) Unit 2, service water system 'B' train past operability due to cross-connect valve leak-by in excess of 1,000 gallons per minute, June 13, 2023

71111.18 - Plant Modifications

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

(1 Sample)

The inspectors evaluated the following temporary or permanent modifications:

(1) Unit 2, temporary modification for the emergency diesel generator engine driven fuel oil pump, Engineering Change Package 2023-1074-001

71111.20 - Refueling and Other Outage Activities

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

(1) The inspectors evaluated Unit 2 refueling outage 2R23 activities from April 8, 2023 to May 15, 2023.

71111.24 - Testing and Maintenance of Equipment Important to Risk

The inspectors evaluated the following testing and maintenance activities to verify system

operability and/or functionality: Post-Maintenance Testing (PMT) (IP Section 03.01)

Main article: IP 71111.24
(1) Unit 2, source range N31 neutron detector nuclear instrumentation channel calibration using procedure 2MSP-2-15-I, April 10, 2023
(2) Unit 2, quench spray pump, 2QSS*P21A, post-maintenance surveillance, May 1, 2023
(3) Unit 1, rod control power supply cabinet, 2AC PNL-ROD-PWR-2AC-PS-1, following the replacement of a failed power supply, per work order (WO) 200913467, May 3, 2023
(4) Unit 2, post-maintenance test of leaking pipe replacement on the supply header to the containment air recirculation fan coils off of the 'B' service water system header, per WO 200893816, May 3, 2023
(5) Unit 2, battery (BAT)-2-5, performance discharge test using procedure 2-PMP-E-39-410, following battery 2-5 replacement, May 8, 2023
(6) Unit 2, emergency diesel generator No. 2, 2EGS*EG2-2 9-hour test using procedure, 2OST-36.2A, following replacement of engine driven fuel pump, May 12, 2023
(7) Unit 2, pressurizer power operated relief valve stroke test using procedure 2OST-6.8, following power operated relief valve replacement during 2R23 refueling outage, May 12, 2023
(8) Unit 2, turbine driven auxiliary feedwater pump operational test using procedure 2OST-24.4A, following outage scope maintenance, May 19, 2023
(9) Unit 1, quench spray pump, 1QS-P-1A, post-maintenance test using procedure 1OST-13.1, June 5, 2023

Surveillance Testing (IP Section 03.01) (3 Samples)

(1) Unit 1, centrifugal charging pump 'B', 1CC-P-1B, quarterly surveillance test using procedure 1OST-15.2, April 7, 2023
(2) Unit 2, containment type 'A' leak test using procedure 2BVT 1.47.2, May 11, 2023
(3) Unit 1, motor driven auxiliary feed pump 'A,' 1FW-P-3A, quarterly surveillance test using procedure 1OST-24.2, May 15, 2023

Inservice Testing (IST) (IP Section 03.01) (2 Samples)

(1) Unit 2, main steam safety valve setpoint Trevitest using procedure 2-MSP-M-21-300, April 8, 2023
(2) Unit 2, high-head safety injection pump 'B' full flow test using procedure 2OST-11.14B, April 27, 2023

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

(1) Unit 2, residual heat removal line penetration #97C type 'C' leak test using procedure 2OST-47.145, April 18, 2023

71114.06 - Drill Evaluation

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

The inspectors evaluated:

(1) An emergency plan training exercise/drill where multiple equipment failures and a large break loss of coolant accident led to a General Emergency declaration on June 8,

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) (2 Samples)

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

(1) Workers exiting containment at Unit 2 during a refueling outage
(2) Workers exiting the radiological controlled area at health check during a refueling outage

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

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

(1) Unit 2 'A' steam generator work
(2) Refueling Unit 2 reactor on the refuel floor
(3) Equipment entry and removal at the Unit 2 containment equipment hatch
(4) Unit 2 'B' steam generator level 2 high contamination area 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 residual heat removal replacement shielding area
(2) Control and inventory of the high radiation area and locked high radiation area keys
(3) Unit 2 reactor head stand locked high radiation area Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 03.06) (1 Sample)
(1) The inspectors evaluated radiation worker and radiation protection technician performance as it pertains to radiation protection requirements.

71124.03 - In-Plant Airborne Radioactivity Control and Mitigation

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

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

(1) Units 1 and 2 main control room emergency ventilation systems

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

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

(1) Evaluate the inventory and use of various high-efficiency particulate air units and vacuums

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

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

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

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

71124.04 - Occupational Dose Assessment

Source Term Characterization (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated licensee performance as it pertains to radioactive source term characterization.

External Dosimetry (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated how the licensee processes, stores, and uses external dosimetry.

Internal Dosimetry (IP Section 03.03) (2 Samples)

The inspectors evaluated the following internal dose assessments:

(1) Reviewed internal dosimetry intake evaluation from May 2023
(2) Reviewed internal dosimetry intake evaluation from April 2023

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

The inspectors evaluated the following special dosimetric situations:

(1) Reviewed declared pregnant program and documents
(2) Reviewed effective dose equivalent for external program and documents

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:

MS05: Safety System Functional Failures (SSFFs) (IP Section 02.04) ===

Main article: IP 71151
(1) Unit 1, April 1, 2022 through March 31, 2023
(2) Unit 2, April 1, 2022 through March 31, 2023

MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)

(1) Unit 1, April 1, 2022 through March 31, 2023
(2) Unit 2, April 1, 2022 through March 31, 2023

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

(1) Unit 1, April 1, 2022 through March 31, 2023
(2) Unit 2, April 1, 2022 through March 31,

INSPECTION RESULTS

No findings were identified.

EXIT MEETINGS AND DEBRIEFS

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

  • On July 13, 2023, the inspectors presented the inservice inspection results to Andrew Crotty, Manager, Work Control, and other members of the licensee staff
  • On July 19, 2023, the inspectors presented the integrated inspection results to Barry Blair, Site Vice President, and other members of the licensee staff
  • On June 29, 2023, the inspectors presented the inspection procedures 71124.03 and 71124.04 inspection results to Barry Blair, Site Vice President, and other members of the licensee staff

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.04 Drawings RM-0410-001 Valve Oper No Diagram Residual Heat Removal Piping 17

RM-0415-001 Valve Oper No Diagram Primary Component Cooling Water 20

RM-0420-001 Valve Oper No Diagram Fuel Pool Cooling and Purification 12

RM-0424-002 Feedwater System 20

71111.05 Fire Plans 1 PFP-SFGB- Aux FW & QS Pumps Fire Compartment 1-QP-1 1

735-AUX

1PFP-DGBX-735- Diesel Generator 2 Room Fire Compartment 1-DG-2 2

DG-2

2PFP-ABBX-730 Auxiliary Boiler 2

2PFP-ABBX-755 Auxiliary Boiler 0

2PFP-RCBX-692 Reactor Containment Building Fire Compartment 2-RC-1 2

2PFP-RCBX-718 Reactor Containment Building Fire Compartment 2-RC-1 2

2PFP-RCBX-738 Reactor Containment Building Fire Compartment 2-RC-1 3

2PFP-RCBX-767 Reactor Containment Building Fire Compartment 2-RC-1 2

2PFP-TRBB-730-

EAST

2PFP-TRBB-730-

WEST

2PFP-TRBB-752-

MEZZ

2PFP-TRBB-774

71111.07A Calculations N-805 1

Corrective Action CR 2020-03259 04/15/2020

Documents CR 2023-03128 04/16/2023

71111.08P Corrective Action 2023-03357

Documents 2023-03587

Corrective Action 2023-03610

Documents

Resulting from

Inspection

Drawings DMW-RV030- Beaver Valley Unit 2 Reactor Vessel Head RVLIS Pipe 0

DW-CY-000001 Repair

Inspection Type Designation Description or Title Revision or

Procedure Date

Engineering ECP-23-1078 Reactor Vessel Head Repair to RVLIS Penetration 2

Changes

Miscellaneous 1/2-ADM-2039 BVPS ISI Ten-Year Plans 19

1/2-ADM-2096 Alloy 600/690 Management Program 17

200913374 Repair Replacement Plan - Reactor Vessel Head Vent Line 02

Penetration

DMW-01-23 Examination Technique Specification Sheet for Bobbin 40 0

IPS

DMW-05-23 Examination Technique Specification Sheet for 3 Coil +PT 0

DMW-06-23 Examination Technique Specification Sheet for Low Row U- 0

B +PT (No DLOC)

DMW-20-23 Examination Technique Specification Sheet for Alloy 800 0

Sleeve G3/G4/+Point Combo

NDE Reports DMW-R23-VL01- Vent ID Post Repair Axial Scan 05/03/2023

AX-CAL-11

DMW-R23-VL01- Vent ID Post Repair Circ Scan 05/03/2023

Circ-CAL-13

Procedures NOP-CC-5740 Liquid Penetrant Examination Visible Dye, Solvent 00

Removable,40-125 Degrees

Work Orders 2009`3374 Reactor Vessel Head Vent Penetration Repair 04/28/2023

71111.11Q Miscellaneous Simulator Guide: Hot Weather Ops 0

G-OTLC-23-35-

HWTHR_BV11

71111.12 Miscellaneous ASME Section IX Welding Procedure Specification (WPS), WPS#1/8-GT-01 2

Procedures 1/2CMP-75- Target Rock Model No. 83C-007 SOV Globe Valve Overhaul 4

TARGET ROCK-

3M

1/2PMP-75-SOV- Target Rock SOV Maintenance for 2MSS-SOV105A thru F 3

2CMP-75- Defeating Blowdown Isolation Due to Opening of 2MSS- 1

DEFEAT BLWDN SOV105A or B

ISOL

2OST-6.8 Pressurizer PORV Stroke Test 20

Work Orders 200796062 04/29/2023

Inspection Type Designation Description or Title Revision or

Procedure Date

200909575

200909576

200909602

71111.13 Corrective Action CR 2023-03437 04/24/2023

Documents

Miscellaneous Risk Management Plan 02/29/2023

2R23 Pre-Outage Defense-in-Depth Report 0

Procedures 2OM-37.4.V De-energizing and Restoring 480VAC Motor Control Centers 4

[MCC*2-E05, E06]

Work Orders 200803212

200803308

200803309

200833538

200833634

200833635

71111.15 Corrective Action 2021-07659 10/12/2021

Documents CR 2022-00889

CR 2023-02904 04/11/2023

CR 2023-03103 04/17/2023

CR 2023-03255

CR 2023-03991 05/12/2023

Corrective Action CR 2023-04050 05/15/2023

Documents CR 2023-04058 05/15/2023

Resulting from

Inspection

Engineering 601407578

Evaluations

Miscellaneous Notification N.

601349198

Procedures 2MSP-2.15-I Nuclear Instrument Source Range N31 Neutron Detector 20

Channel Calibration

2OM-10.4.B Residual Heat Removal System Running 34

NOP-OP-1014 Plant Status Control 08

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.18 Engineering 23-1074-001 Design Equivalent Change Package 1

Changes

71111.24 Corrective Action CR 2023-03579

Documents CR 2023-03649 04/30/2023

Drawings RM-0415-001

Procedures 1OST-13.1 Quench Spray Pump [1QS-P-1A] Test 49

1OST-15.2 [1CC-P-1B] Quarterly Test 51

1OST-24.2 Motor Driven Auxiliary Feed Pump Test [1FW-P-3A] 58

2-MSP-M-21-300 Issue 4 1

2-PMP-E-39-410 Battery [BAT-2-5] Performance Discharge Test 4

2BVT 1.47.2 Containment Type A Leak Test 4

2MSP-2.15.I Nuclear Instrumentation Source Range N31 Neutron 20

Detector Channel Calibration

2OST-11.14B HHSI Full Flow Test 45

2OST-24.4A Turbine Driven Auxiliary Feedwater Pump [2FWE*P22] Test 42

2OST-36.2A Emergency Diesel Generator [2EGS*EG2-2] 9-Hour Test 8

2OST-47.145 Type C Leak Test - Penetration #97-C (Residual Heat 1

Removal Sample Line_

2OST-6.8 Pressurizer PORV Stroke Test 20

2QSS*P21A Quench Spray Pump [2Qss*P21A] Test 38

Work Orders 200751309

200848565 04/09/2023

200893816 05/03/2023

200911671 04/09/2023

200913467 05/03/2023

71114.06 Miscellaneous 2023 ERO

Focused Area

Drill - Cycle 2

16

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