IR 05000334/2022004
| ML23040A089 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/09/2023 |
| From: | Matt Young Division of Operating Reactors |
| To: | Blair B Energy Harbor Nuclear Corp |
| References | |
| IR 2022004 | |
| Download: ML23040A089 (1) | |
Text
February 9, 2023
SUBJECT:
BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000334/2022004 AND 05000412/2022004
Dear Barry Blair:
On December 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Beaver Valley Power Station, Units 1 and 2. On January 12, 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:
05000334/2022004 and 05000412/2022004
Enterprise Identifier: I-2022-004-0031
Licensee:
Energy Harbor Nuclear Corporation
Facility:
Beaver Valley Power Station, Units 1 and 2
Location:
Shippingport, PA 15077
Inspection Dates:
October 1, 2022 to December 31, 2022
Inspectors:
G. Eatmon, Senior Resident Inspector
B. Edwards, Health Physicist
E. Eve, Senior Reactor Inspector
R. Rolph, Resident Inspector
B. Towne, Senior Resident Inspector
S. Wilson, Senior Health Physicist
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 began the inspection period at rated thermal power. Unit 1 was shutdown on October 9, 2022, for a refueling outage. Unit 1 was returned to rated thermal power on November 24, 2022, and remained at or near rated thermal power for the remainder of the inspection period.
Unit 2 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, 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
Impending Severe Weather Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the readiness for seasonal extreme weather conditions prior to the onset of very cold temperatures for the Units 1 and 2 refueling water storage tanks, the intake structure, and the alternate intake structure during the week of December 19, 2022.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1, residual heat removal system train 'A' and 'B' during lowered reactor coolant system inventory, October 13, 2022
- (2) Unit 1, 'A' and 'B' trains of auxiliary feedwater system, December 13, 2022
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (2 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, primary auxiliary building 768' and 752' and fire compartments, fire areas 1PFP-AXLB-768, 1PFP-ALXB-752, 1-PA-1C and 1-PA-1A, October 12, 2022
- (2) Unit 1, safeguards during 1R28 refueling outage and associated hot work, October 28, 2022
71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)
- (1) The inspectors verified that the Unit 1 reactor coolant system boundary, steam generator tubes, 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 October 17 to October 31, 2022:
03.01.a - Nondestructive Examination (NDE) and Welding Activities
- Direct observation of ultrasonic testing of safety injection system weld, SI-262-1502-Q1, NDE Report No.: UT-22-1020
- Direct observation of liquid penetrant testing of recirculation spray pump 2A welded attachment weld, RS-P-2A-A-7, NDE Report No.: PT-22-1001
- Remote observation of visual and ultrasonic testing examination of baffle former bolts per MRP-227 and MRP-228, CR-2022-08109
- Record review of reactor vessel lower head bare metal visual inspection of nozzles per American Society of Mechanical Engineers Code Case N-722, NDE Report No.: VT-22-1030
- Record review of visual examination of pressurizer lower instrument nozzles in response to insulation impact, CR-2022-07981 and NDE Report no.: BOP-VT-22-015
03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities
- Record review of reactor head penetration 47 visual re-examination, NDE Report No.: BOP-VT-22-012
03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities
- CR-2019-10355, evaluation for active boric acid leakage past threaded cap of 4-way fitting downstream of 1QS-88 ( (1QS-P-1A) bearing water supply isolation valve)
- CR-2022-07894, evaluation for active boric acid leak was identified on RV-1DA-101, thermal relief valve for containment penetration # 38
- CR-2022-07556, corrective actions associated with an active boric acid leak on 1QS-4, 1B quench spray pump discharge check valve
- CR-2022-07908, corrective actions associated with dry boric acid identified on MOV-1RC-535, pressurizer power operated relief valve isolation motor operated valve 03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities
- Direct remote observation of eddy current testing of 1A, 1B, and 1C steam generators
- Video review of 1A secondary side visual examinations
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 the planned shutdown of Unit 1 for refueling outage 1R28 on October 8-9, 2022.
71111.12 - Maintenance Effectiveness
Quality Control (IP Section 03.02) (2 Samples)
The inspectors evaluated the effectiveness of maintenance and quality control activities to ensure the following structures, systems, and components remain capable of performing its intended function:
- (1) Unit 1, recirculation spray diaphragm as-found weld inspection of the 'A' and 'C' heat exchangers, October 16, 2022; and as-left weld inspection, October 22, 2022
- (2) Unit 1, 480 volt stub bus supply breaker (9P16) failed to trip when signal received, December 9, 2022
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (6 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, elevated risk for planned power reduction for maintenance that removed all the moisture separator reheaters from service, October 3, 2022
- (2) Unit 1, elevated risk due to 'B' loop cold leg isolation valve, MOV-1RC-593, bound and will not open to isolate the loop for a planned steam generator inspection during the refueling outage, October 10, 2022
- (3) Unit 2, elevated risk due to a heavy load lift on reactor coolant filter in the auxiliary building, October 31, 2022
- (4) Unit 1, component misposition event de-energized vital bus 2 while the unit was in no mode, November 1, 2022
- (5) Unit 1, emergent work on the 'A' steam generator throttle valve, MOV-1FW-151E, from the 'B' train auxiliary feedwater header would not open in Mode 3, November 16, 2022
- (6) Unit 1, emergent work on 1A feedwater pump due to loss of oil. Loss of pump would result in 50 percent power limit during the week of December 12, 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) Unit 2, service water pump 21C high shaft inner column water pressure due to outer shaft leakage, September 16, 2022
- (2) Unit 2, service water train 'B' due to leak on the containment air recirculation cooling coil supply line, October 9, 2022
- (3) Unit 1, eleven feet of pressurizer circumferential insulation slid 18 inches down tank while being removed for inspection during 1R28, resting on various pressurizer nozzles causing physical observable deflection to five nozzles, October 21, 2022
- (4) Unit 2, terry turbine steam isolation valve slow stroke closed, December 1, 2022
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) Unit 1, permanent modification of tubing downstream of 1RC-272 support relocation in Engineering Change Package 22-1073-001
- (2) Unit 1, replacement of Flowserve double disk gate valve wedge pin and threaded stem to upper wedge connection in the low head safety injection to reactor coolant system cold leg motor operated valve, MOV-1SI-890C, and reuse existing lower wedge, October 12, 2022
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system operability and/or functionality:
- (1) Unit 1, static test of MOV-1SI-890C valve operator, low head safety injection to reactor cooling system cold leg, after anchor darling gate valve wedge pin and stem replacement, October 12, 2022
- (2) Unit 1, relay trip checks associated with safety-related electrical bus AE outage, October 23, 2022
- (3) Unit 1, emergency diesel generator 1-1 surveillance to verify operation of breaker 4KV-1AE-1E9, the incoming supply breaker from 1-1 emergency diesel generator to
'AE' emergency switch gear, after a ground was identified, October 25, 2022
- (4) Unit 1, emergency diesel generator 1-2, after replacing two air start valves and an oil change, November 1, 2022
- (5) Unit 1, 'B' motor driven auxiliary feedwater pump following bearing inspection, November 5, 2022
- (6) Unit 2, emergency diesel generator 2-1, after rebuilding temperature control valve, EDG-RS-201, that caused excess condensation in the engine intercooler, December 1, 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 1R28 activities from October 9 to November 19, 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) (1 Sample)
- (1) Unit 2, 2SIS-P21A, "Low Head Safety Injection Pump Test," Revision 33, November 1, 2022
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) Unit 1, leak test on 1X-89, "Condenser Air Ejector Discharge to Containment," October 13,
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 the radiologically controlled area at Unit 1 during a refueling outage
- (2) Evaluated how radiation protection personnel supported removal of an injured worker from Unit 1 containment building
Radiological Hazards Control and Work Coverage (IP Section 03.04) (4 Samples)
- (1) Nozzle dam insertion for Unit 1 B steam generator under Radiation Work Permit Number 122-4017
- (2) Insert removal for Unit 1 B steam generator under Radiation Work Permit Number 122-4017
- (3) Removal of robot from Unit 1 C steam generator under Radiation Work Permit Number 122-4017
- (4) Removal of seal package from Unit 1 B reactor coolant pump under Radiation Work Permit Number 122-4025
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) Units 1 and 2 high radiation area key storage, controls, and inventory system
- (2) Unit 1 reactor head stand locked high radiation area controls
- (3) Unit 1 B steam generator cubicle
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.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10)===
- (1) Unit 1, October 1, 2021 through September 30, 2022
- (2) Unit 2, October 1, 2021 through September 30, 2022
BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)
- (1) Unit 1, October 1, 2021 through September 30, 2022
- (2) Unit 2, October 1, 2021 through September 30, 2022
OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)
- (1) October 1, 2021 through October 1, 2022
PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)
- (1) October 1, 2021 through October 1, 2022
71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) The inspectors conducted an in-depth review of the corrective actions for multiple check source failures in Unit 2.
71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)
- (1) The inspectors reviewed the licensees risk assessment practices for emergent maintenance for potential adverse trends that might be indicative of a more significant safety issue.
INSPECTION RESULTS
Observation: Annual Review of Risk Challenge Review Boards for Emergent Maintenance 71152S Inspectors investigated a potential adverse trend in risk assessment for emergent maintenance. Inspectors found that the licensee began performing inter-disciplinary risk challenge meetings for emergent maintenance following consecutive Unit 2 reactor trips in the fall of 2021 and multiple Unit 1 reactor trips in the spring of 2022. The inspectors determined that, in most cases, the risk associated with emergent maintenance was appropriately evaluated by licensee staff and mitigating actions were effectively implemented.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On January 12, 2023, the inspectors presented the integrated inspection results to Barry Blair, Site Vice President, and other members of the licensee staff.
- On October 27, 2022, the inspectors presented the inservice inspection activities inspection results to Steve Sawtschenko, Manager, Regulatory Compliance and Emergency Preparedness, and other members of the licensee staff.
- On October 20, 2022, the inspectors presented the radiation protection radiological hazards and control inspection results to Bob Kristophel, General Plant Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR 2021-00999
Alternate Intake Structure Furnace Power Supply Handle
Not Functioning
2/16/2021
CR 2021-01421
Alternate Intake Furnace Won't Fire
03/02/2021
CR 2021-06940
Damaged Insulation
09/15/2021
CR 2021-09607
Permanent Structure Instead of Temporary Tents
2/20/2021
CR 2021-9611
Temporary Heathers Not Ready
2/20/2021
Procedures
1/2-ADM-2029
Temporary Configuration Control
1/2OST-45.1
Extreme Cold Weather Protection Verification
Drawings
RM-0018A
Flow Diagram Feed Water
RM-0410-001
Piping and Instrumentation Diagram Residual Heat Removal
System
Fire Plans
Auxiliary Building General Area Fire Compartment 1-PA-1C
Auxiliary Building General Area Fire Compartment 1-PA-1A
Safeguards Area Fire Compartment 1-PT-1
AUX
AUX FW & QS Pumps Fire Compartment 1-QP-1
EAST
East Cable Vault Fire Compartment 1-CV-2
WEST
West Cable Vault Fire Compartment 1-CV-1
71111.11Q Procedures
1OM-52.4.R.1.F
Station Shutdown from 100 Percent Power to Mode 5
Corrective Action
Documents
CR 2021-03368
CR 2022-08268
Work Orders
Corrective Action
Documents
CR 2022-07619
CR 2022-07805
CR 2022-08294
CR 2022-08786
CR 2022-09477
Procedures
1/2-ADM-0819
Handling of NUREG 0612 Heavy Loads
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1OM-
53C.4.1.38.1B
Loss of Vital Bus II
1OST-24,9
Turbine-Driven AFW Pump (1FW-P-2) Operability Test
01/05/2022
1OST-24.1
SG Aux Feed Pumps Throttle Valve Stroke From Control
Room
10/26/2018
2OM-26.4.S
Isolation of Turbine Moisture Separator Reheat Section
NOP-OP-1007-01
Risk Management Plan
Calibration
Records
Calculation Package, "Beaver Valley SW Branch Line N-513
Evaluation," Structural Integrity Associates, Inc.
10/09/2022
Corrective Action
Documents
CR 2021-01889
CR 2021-04525
CR 2022-06668
CR 2022-06851
09/08/2022
CR 2022-07059
09/16/2022
CR 2022-07530
10/07/2022
CR 2022-07555
10/09/2022
CR 2022-07981
CR 2022-08953
Engineering
Evaluations
EER 601376944
Engineering Evaluation Request for Flaw and Wall Thinning
10/08/2022
EER 601377626
Evaluate Long Term Operation of 2SWS-P21C
10/13/2022
Engineering
Evaluation
Request
601003686
IST Pre-Conditioning Evaluation
Miscellaneous
N-513-4
American Society of Mechanical Engineers Evaluation
Criteria for Temporary Acceptance of Flaw in Moderate
Energy Class 2 or 3 Piping
05/07/2014
Corrective Action
Documents
CR 2022-00451
CR 2022-07671
CR 2022-07981
Engineering
Changes
ECP-22-1073-001 Tubing Downstream of 1RC-272 Support Relocation
Engineering
Engineering
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Evaluations
Evaluation
Request
601378751
Procedures
LTR-CECO-22-
096
Evaluation of Beaver Valley Unit 1 Bent Pressurizer
Instrumentation Nozzles
PERP-001312
Part Equivalent Replacement Package for Anchor Daring
Gate Valve Wedge Pin Material Upgrade
10/12/2022
Recommendations to Resolve Flowserve 10CFR Part 21
Notification Affecting Anchor Daring Double Disk Gate Valve
Wedge Pin Failures
Corrective Action
Documents
CR 2022-08069
CR 2022-08383
CR 2022-09133
Miscellaneous
NORM-WM-
4006A
Conduct of Maintenance Handbook
Procedures
Clearing and Returning to Service Emergency 4KV Bus 1AE
1OST-24,3
Motor Driven Auxiliary Feed Pump Test [1FW-P-38]
1OST-36.2
Diesel Generator No. 2 Monthly Test
2OST-36.1
Emergency Diesel Generator Monthly Test
LUC PAF-22-
06145, 1OST-
36.1
Diesel Generator No. 1 Monthly Test
10/24/2022
Work Orders
Procedures
1OM-52.4.B
Load Following
1OST-47.2B
Containment Closeout Inspection
1RST02,1
Initial Approach to Critically After Refueling, Issue 1
Procedures
Inservice Testing (IST) Program for Pumps and Valves,
Issue 4
1OST-47.152
Type C Test - Penetration #89 (Main Condenser Ejector
Vent)
2OST-11.1
Low Head Safety Injection Pump Test
71151
Corrective Action
Documents
CR 2022-04716
Corrective Action
CR 2019-03658
2MSS-RQ101A Abnormal High Reading
04/18/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Documents
CR 2021-04027
2MSS-RQ101B Alert Alarm
05/18/2021
CR 2022-03110
2MSS-DAU102A Failed Source Check
04/07/2022
CR 2022-06046
Failed Check Source on 2MSS-RQ101B
08/05/2022
CR 2022-06704
2MSS-RQ101B Failed Check Source
08/31/2022
CR 2022-06760
Evaluate Extent of Condition for Radiation Monitor Check
Source Degradation
09/02/2022
CR 2022-06936
2MSS-RQ101C Main Steam Line Monitor Check Source
Failure
09/12/2022
CR 2022-08430
Equipment Reliability Issue - Unit 2 Cs-137 Radiation
Monitor Calibration Sources