IR 05000334/2023002
| ML23221A024 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/09/2023 |
| From: | Matt Young Division of Operating Reactors |
| To: | Blair B Energy Harbor Nuclear Corp |
| References | |
| IR 2023002 | |
| Download: ML23221A024 (1) | |
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, 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:
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
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)===
The inspectors verified that the following nondestructive examination and welding activities were performed appropriately:
- (1) Eddy Current Examination
- Automated eddy current test of the reactor pressure vessel (RPV) head, vent line ID scan (Nondestructive Examination (NDE) Report DMW-R23-VL01-ID-01)
- Automated eddy current test of the RPV head, vent line Jweld scan (NDE Report DMW-R23-VJ01-Jweld-01)
- 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
- 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-2021-08229, for the 2CHS-472 check valve of the chemical and volume control system
- 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
- CR-2023-03268, for the 2RCS-MOV591 loop 'A' cold leg isolation valve body to bonnet area of the reactor coolant system
PWR Inservice Inspection Activities - Steam Generator Tube Inspection Activities (Section 03.04) (1 Sample)
The inspectors verified that the licensee is monitoring the steam generator tube integrity appropriately through a review of the following examinations:
(1)
- Eddy current testing of inservice tubes in steam generators A, B, and C
- Secondary side visual examinations in steam generators A, B, and C
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) (9 Samples)
- (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)===
- (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
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
RM-0410-001
Valve Oper No Diagram Residual Heat Removal Piping
RM-0415-001
Valve Oper No Diagram Primary Component Cooling Water
RM-0420-001
Valve Oper No Diagram Fuel Pool Cooling and Purification
RM-0424-002
Feedwater System
Fire Plans
PFP-SFGB-
735-AUX
Aux FW & QS Pumps Fire Compartment 1-QP-1
DG-2
Diesel Generator 2 Room Fire Compartment 1-DG-2
Auxiliary Boiler
Auxiliary Boiler
Reactor Containment Building Fire Compartment 2-RC-1
Reactor Containment Building Fire Compartment 2-RC-1
Reactor Containment Building Fire Compartment 2-RC-1
Reactor Containment Building Fire Compartment 2-RC-1
EAST
WEST
MEZZ
Calculations
N-805
Corrective Action
Documents
CR 2020-03259
04/15/2020
CR 2023-03128
04/16/2023
Corrective Action
Documents
23-03357
23-03587
Corrective Action
Documents
Resulting from
Inspection
23-03610
Drawings
DMW-RV030-
DW-CY-000001
Beaver Valley Unit 2 Reactor Vessel Head RVLIS Pipe
Repair
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Changes
ECP-23-1078
Reactor Vessel Head Repair to RVLIS Penetration
Miscellaneous
1/2-ADM-2039
1/2-ADM-2096
Alloy 600/690 Management Program
200913374
Repair Replacement Plan - Reactor Vessel Head Vent Line
DMW-01-23
Examination Technique Specification Sheet for Bobbin 40
DMW-05-23
Examination Technique Specification Sheet for 3 Coil +PT
DMW-06-23
Examination Technique Specification Sheet for Low Row U-
B +PT (No DLOC)
DMW-20-23
Examination Technique Specification Sheet for Alloy 800
Sleeve G3/G4/+Point Combo
NDE Reports
DMW-R23-VL01-
AX-CAL-11
Vent ID Post Repair Axial Scan
05/03/2023
DMW-R23-VL01-
Circ-CAL-13
Vent ID Post Repair Circ Scan
05/03/2023
Procedures
NOP-CC-5740
Liquid Penetrant Examination Visible Dye, Solvent
Removable,40-125 Degrees
Work Orders
2009`3374
Reactor Vessel Head Vent Penetration Repair
04/28/2023
71111.11Q Miscellaneous
Simulator Guide:
G-OTLC-23-35-
HWTHR_BV11
Hot Weather Ops
Miscellaneous
Welding Procedure Specification (WPS), WPS#1/8-GT-01
Procedures
1/2CMP-75-
TARGET ROCK-
3M
Target Rock Model No. 83C-007 SOV Globe Valve Overhaul 4
1/2PMP-75-SOV-
Target Rock SOV Maintenance for 2MSS-SOV105A thru F
DEFEAT BLWDN
ISOL
Defeating Blowdown Isolation Due to Opening of 2MSS-
SOV105A or B
2OST-6.8
Pressurizer PORV Stroke Test
Work Orders
200796062
04/29/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
200909575
200909576
200909602
Corrective Action
Documents
CR 2023-03437
04/24/2023
Miscellaneous
Risk Management Plan
2/29/2023
2R23 Pre-Outage Defense-in-Depth Report
Procedures
2OM-37.4.V
De-energizing and Restoring 480VAC Motor Control Centers
[MCC*2-E05, E06]
Work Orders
200803212
200803308
200803309
200833538
200833634
200833635
Corrective Action
Documents
21-07659
10/12/2021
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
Documents
Resulting from
Inspection
CR 2023-04050
05/15/2023
CR 2023-04058
05/15/2023
Engineering
Evaluations
601407578
Miscellaneous
Notification N.
601349198
Procedures
2MSP-2.15-I
Nuclear Instrument Source Range N31 Neutron Detector
Channel Calibration
2OM-10.4.B
Residual Heat Removal System Running
NOP-OP-1014
Plant Status Control
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Engineering
Changes
23-1074-001
Design Equivalent Change Package
Corrective Action
Documents
CR 2023-03579
CR 2023-03649
04/30/2023
Drawings
RM-0415-001
Procedures
1OST-13.1
Quench Spray Pump [1QS-P-1A] Test
1OST-15.2
[1CC-P-1B] Quarterly Test
1OST-24.2
Motor Driven Auxiliary Feed Pump Test [1FW-P-3A]
2-MSP-M-21-300
Issue 4
2-PMP-E-39-410
Battery [BAT-2-5] Performance Discharge Test
2BVT 1.47.2
Containment Type A Leak Test
2MSP-2.15.I
Nuclear Instrumentation Source Range N31 Neutron
Detector Channel Calibration
2OST-11.14B
HHSI Full Flow Test
2OST-24.4A
Turbine Driven Auxiliary Feedwater Pump [2FWE*P22] Test
2OST-36.2A
Emergency Diesel Generator [2EGS*EG2-2] 9-Hour Test
2OST-47.145
Type C Leak Test - Penetration #97-C (Residual Heat
Removal Sample Line_
2OST-6.8
Pressurizer PORV Stroke Test
2QSS*P21A
Quench Spray Pump [2Qss*P21A] Test
Work Orders
200751309
200848565
04/09/2023
200893816
05/03/2023
200911671
04/09/2023
200913467
05/03/2023
Miscellaneous
23 ERO
Focused Area
Drill - Cycle 2