IR 05000334/2021002
| ML21223A202 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/11/2021 |
| From: | Matt Young Division of Operating Reactors |
| To: | Grabnar J Energy Harbor Nuclear Corp |
| Young M | |
| References | |
| IR 2021002 | |
| Download: ML21223A202 (23) | |
Text
August 11, 2021
SUBJECT:
BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - INTEGRATED INSPECTION REPORT 05000334/2021002 AND 05000412/2021002
Dear Mr. Grabnar:
On June 30, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Beaver Valley Power Station, Units 1 and 2. On July 21, 2021, 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 5 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:
05000334/2021002 and 05000412/2021002
Enterprise Identifier: I-2021-002-0032
Licensee:
Energy Harbor Nuclear Corporation
Facility:
Beaver Valley Power Station, Units 1 and 2
Location:
Shippingport, PA 15077
Inspection Dates:
April 1, 2021 to June 30, 2021
Inspectors:
G. Eatmon, Senior Resident Inspector
R. Rolph, Resident Inspector
L. Cline, Senior Project Engineer
K. Chambliss, Project Engineer
T. Fish, Senior Operations Engineer
T. Hedigan, Operations Engineer
J. Rady, Senior Emergency Preparedness Inspect
A. Turilin, Reactor Inspector
Approved By:
Matt R. Young, Chief
Projects Branch 5
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 96.5 percent rated thermal power for the end-of-cycle coast down operations for the planned refueling outage. The refueling outage began on April 11, 2021, and lasted through May 10, 2021, when the reactor trip breakers closed and 100 percent rated thermal power was reached on May 14, 2021. On May 18, 2021, the unit decreased power to 28 percent to repair the normal level control valve for the heater drain system and returned to rated thermal power on May 20, 2021. On June 11, 2021, the unit detected a condenser tube leak and reduced power to 80 percent for repairs, then returned the unit to rated thermal power on June 14, 2021. Unit 1 operated 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 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.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the coronavirus (COVID-19), resident and regional inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week, increasing the amount of time on site as local COVID-19 conditions permitted.
As part of their onsite activities, resident inspectors conducted plant status activities as described in IMC 2515, Appendix D; observed risk significant activities; and completed on site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or a portion of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1, unborated water source isolation valves (1CH-90, 1CH-91, and 1CH-93) per Technical Specification 3.1.8, on April 14, 2021
- (2) Unit 1, spent fuel pool cooling system, train 'A' and train 'B' while in elevated yellow risk, on April 21, 2021
- (3) Unit 1, low head safety injection pump 'A' boric acid flow path after full flow test on April 23, 2021
- (4) Unit 2, recirculation spray, train 'C' on May 21, 2021
- (5) Unit 1, quench spray system, train 'B' after the quarterly pump test on May 23, 2021
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the accessible portions and system configurations during a complete walkdown of the Unit 2 low head safety injection system A on May 21, 2021
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (6 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, Auxiliary Building (elevations 735', 752', and 768') on April 21, 2021
- (2) Unit 1, 693 East and West Turbine Building on April 22, 2021
- (3) Unit 1, 713 Turbine Building Mezzanine on April 22, 2021
- (4) Unit 1, 735 Turbine Building Operating Deck on April 22, 2021
- (6) Unit 1 and Unit 2, Outage Central on May 6, 2021
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an unannounced fire drill in the Unit 1 and Unit 2 Intake Structure, B Pump Cubicle on June 22, 2021
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) Unit 1, primary auxiliary building elevations 768'-7" (flood zone PA-1A), 752'-6" (flood zone PA-1C), 735'-6" (flood zone (PA-1E) and 722'-6" (flood zone PA-1G) on May 28, 2021
Cable Degradation (IP Section 03.02) (1 Sample)
The inspectors evaluated cable submergence protection in:
- (1) Manholes associated with the Unit 1 and Unit 2 main intake for river water and service water:
- 1EMH8A
- 1EMH8B
- 1EHM15
71111.07A - Heat Sink Performance
Annual Review (IP Section 03.01) (1 Sample)
The inspectors evaluated readiness and performance of:
- (1) Unit 1, recirculation spray heat exchangers during 1R27 outage:
71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)
- (1) The inspectors verified that the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from April 19 through April 29, 2021:
03.01.a - Nondestructive Examination and Welding Activities.
- Manual ultrasonic testing of the 'A' steam generator circumferential weld, RC-E-1A-C-1 (NDE Report UT-21-1017)
- Manual ultrasonic testing of reactor coolant drain line socket weld RC-43-1502-Q1 per MRP-146 (NDE Report UT-21-1001, WO 200786922)
- Manual ultrasonic testing of safety injection butt welded vertical upward line, SI-260-1502-Q1 per MRP-146 (NDE Report UT-21-1014)
- Manual ultrasonic testing of safety injection butt weld, SI-72-8-S-01. This weld contained a relevant indication that was accepted for continued service. (NDE Report UT-21-1002)
- General visual examinations of the primary containment accessible metal liner surfaces (1BVT 1.47.1 Containment Structural Integrity Test, WO 200784278).
- Welding activities associated with recirculation spray heat exchanger 1RS-E-1C tube plugging EC 632678 (WO 200787033)
03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities.
- Harbor Energy did not perform reactor vessel upper head penetration examinations during this outage. The last head inspection visual examination was in fall 2019 (1R26) outage.
03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.
- Boric Acid on Core Exit Thermocouple Nozzle Assembly (CETNA) (CR-2021-
===02891)
- Boric Acid on BIT Out Vent BV-1SI-353 (CR-2021-02908)
- Boric Acid on 1QS-4 check valve (CR-2021-02872)
- Boric Acid identified on reactor BVPS-1 reactor vessel head due to cleaning of core exit thermocouples during outage (CR-2021-02956)
03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities.
- Per Issuance of Amendment No. 310 "One-Time Extension of Unit No.1 Steam Generator Inspections (COVID-19), dated March 22, 2021, the spring of 2021 (1R27) refueling outage Steam Generator inspections was deferred to the fall of 2022 (1R28) refueling outage.
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03)===
- (1) The inspectors reviewed and evaluated the Unit 2 licensed operator examination failure rates for the requalification annual operating exams administered May through June 2021, and the requalification biennial written exams administered February through April 2021
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)
- (1) Biennial Requalification Written Examinations
The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered February through April 2021.
Annual Requalification Operating Tests
The inspectors evaluated the adequacy of the facility licensees annual requalification operating test.
Administration of an Annual Requalification Operating Test
The inspectors evaluated the effectiveness of the facility licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the facility licensee is effectively evaluating their licensed operators for mastery of training objectives.
Requalification Examination Security
The inspectors evaluated the ability of the facility licensee to safeguard examination material, such that the examination is not compromised.
Remedial Training and Re-examinations
The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions
The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.
Control Room Simulator
The inspectors evaluated the adequacy of the facility licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
Problem Identification and Resolution
The inspectors evaluated the licensees ability to identify and resolve problems associated with licensed operator performance.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the Control Room during Unit 1 power reduction and transition from Mode 1 to Mode 3 on April 10 through 11, 2021
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a simulator training for a station blackout event on Unit 2 on June 22, 2021
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (5 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 1 and Unit 2, risk management for opening common control room pressure boundary door during Unit 1 refueling outage, 1R27, for battery 1-5 replacement, while Unit 2 remains at full power on April 19, 2021
- (2) Unit 1, Yellow defense-in-depth risk condition for decay heat removal and spent fuel pool cooling that on 'A' reactor component cooling heat exchanger for heat removal while performing maintenance on the 'B' and 'C' reactor component cooling heat exchangers on April 20, 2021
- (3) Unit 1, emergent work on turbine driven auxiliary feedwater pump to replace the governor after pump tripped twice during the surveillance and the governor was oscillating with possible overspeed trips on May 9, 2021
- (4) Unit 1, power reduction to 28 percent to remove the heater drain system, a balance of plant system, from service when the normal level control switch for the heater drain tank was not controlling level as expected and the heater drain tank high level dump was cycling on May 17, 2021
- (5) Unit 1, power reduction to 80 percent to identify and repair main condenser tube leakage, on June 12, 2021
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (6 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Unit 1, required flow to the 'A' train recirculation spray heat exchangers not met with the reactor plant river pump 'C', 1WR-P-1C, in service on March 16, 2021
- (2) Unit 1, pressurizer safety valve leakby with valve RV-1RC-551B with low reactor coolant system pressure on May 4, 2021
- (3) Unit 2, service water system train 'B' pipe leak upstream of service water vent valve, 2SWS-1210, in pump bay 'C' on May 5, 2021
- (4) Unit 1, displaced concrete discovered in containment after type 'A' testing on May 7, 2021
- (5) Unit 2, leakage discovered near valve 2SWS-MOV120A revealed a linear flaw near the weld, that when characterized, rendered service water system train 'A' inoperable on May 27, 2021
- (6) Unit 1, control room ventilation, 1VS-AC-1B, used breaker 9P10 instead of breaker 9P3 on June 14, 2021
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) ECP-21-0051, Evaluate an alternative secondary 480VAC power source for the Unit 2 digital rod position indication to eliminate the single point vulnerability from both sources using the same 480VAC bus on May 27, 2021
- (2) ECP 20-0107-001, raise the Unit 2 C steam generator level deviation alarm high limit from 49 percent to 54 percent and ECP 20-0189-001, incorporate the changes made in Temp Mod ECP-20-0107 to raise the Unit 2 C steam generator level deviation alarm high limit from 49 percent to 54 percent into a permanent modification on June 29, 2021
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Unit 1, 1OST-36.2, Diesel Generator No. 2 Monthly Test, after completion of fuel injector testing (WO 200797825) and overspeed trip mechanism inspection (WO
===200796178) on April 19, 2021
- (2) Unit 1, vanstone liner inspection and replacement on pipeline from CC-E-1B to WR-17 using WO200830416 and pipeline from CC-E-1C to WR-17 using WO200830417 on April 30, 2021
- (3) Unit 1, 1OST-36.1, Diesel Generator No. 1 Monthly Test, after cleaning and replacing the thermostats, cooling water heat exchanger inspection and air start motors repairs on May 3, 2021
- (4) Unit 1, accumulators, SI-TK-1A, SI-TK-1B, and SI-TK-1C, boron concentration reduction to maintain technical specification margin on May 4, 2021
- (5) Unit 1, flux map after 'A' traversing incore replacement on May 8, 2021
- (6) Unit 1, pressurizer relief valve, BV-PCV-1RC-455C and BV-PCV-1RC-456, replacement on May 9, 2021
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01)===
- (1) The inspectors evaluated refueling outage 1R27 activities from April 10, 2021 through May 14, 2021
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Unit 1, high head safety injection full flow test on April 26, 2021
- (2) Unit 1, type 'B' leak rate test of the containment equipment hatch on April 30, 2021
- (3) Unit 1, type 'A' leak test of primary reactor building containment verifies containment integrity every 10 years on May 1, 2021
- (4) Unit 1, reactor plant river water system, train 'A', full flow test on May 19, 2021
- (5) Unit 1, reactor plant river water, train 'A', valve stroke testing on May 20, 2021
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) Unit 1, low head safety injection pumps, 1SI-P-1A and 1SI-P-1B, full flow test on April 20, 2021
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) Unit 1, type 'C' leak test of quench spray header 'A', penetration #64 using WO200743628, and quench spray header 'B', penetration #63 using WO200743627
FLEX Testing (IP Section 03.02) (1 Sample)
- (1) Unit 1 and Unit 2, reactor coolant system boration pump operational inspection and performance test on April 30, 2021
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.01-02.04) (1 Sample)
- (1) The inspectors evaluated the licensee's maintenance and testing of the Beaver Valley alert and notification system on June 7 through June 10, 2021, for the period of June 2019 through May 2021
71114.03 - Emergency Response Organization Staffing and Augmentation System
Inspection Review (IP Section 02.01-02.02) (1 Sample)
- (1) The inspectors evaluated the readiness of the licensee's Emergency Preparedness Organization on June 7 through June 10, 2021
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated the following submitted Emergency Action Level and Emergency Plan changes onsite on June 7 through June 10, 2021.
- BV-2020-026-00, EPP-PLAN-SECTION-6, Emergency Measures, Revision 37
- BV-2020-026-00, EPP-PLAN-APPENDIX-F, Warning Sirens, Revision 20
This evaluation does not constitute NRC approval.
71114.05 - Maintenance of Emergency Preparedness
Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
- (1) The inspectors evaluated the maintenance of the emergency preparedness program on June 7 through June 10, 2021, for the period of June 2019 through May
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)
The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas.
- (1) The inspectors reviewed the following:
Radiation Work Packages
- 121-4028 Unit 1 Scaffolding
- 121-4061 Unit 1 Test and Repair TV-1CH-200A
- 121-4018 Unit 1 Reactor Disassembly, Reassembly, Preparations and Inspections
- 121-4021 Unit 1 Remove and Replace the Reactor Head and Upper Internals
- 121-4023 Unit 1 ISI Support
Electronic Alarming Dosimeter Alarms
- No alarms occurred during the period of this inspection
Labeling of Containers
- Various containers in the Unit 1 Primary Auxiliary Building 735' PCA shop area
- Various containers in the Unit 1 Containment Building
Contamination and Radioactive Material Control (IP Section 03.03) (2 Samples)
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.
- (1) Observed Personnel and Equipment leaving the Step Off Pad at the Unit 1 Containment access area inside the Unit 1 Primary Auxiliary Building during the refueling outage
- (2) Observed workers and equipment exiting the Unit 2 main RCA exit point during the Unit 1 refueling outage
Radiological Hazards Control and Work Coverage (IP Section 03.04) (3 Samples)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.
- (1) The inspectors also reviewed and then observed the radiological work package for down posting a Very High Radiation Area, to a Locked High Radiation Area, and then to a High Radiation Area
- (2) The inspectors also reviewed and then observed the radiological work package for the repair of TV-1CH-200A in the Regenerative Heat Exchanger Locked High Radiation Area
- (3) There were no work packages to review for areas with airborne radioactivity during this inspection
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 1 Regenerative Heat Exchanger room inside Containment
- (2) Unit 1 Very High Radiation Area at the entrance to the "Keyway" to under the vessel prior to down posting
- (3) Unit 1 Area leading to under the Reactor Vessel head while on the head Stand in the Containment basement
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:
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)===
- (1) Unit 1 April 1, 2020 through March 31, 2021
- (2) Unit 2 April 1, 2020 through March 31, 2021
MS06: Emergency AC Power Systems (IP Section 02.05) (2 Samples)
- (1) Unit 1 April 1, 2020 through March 31, 2021
- (2) Unit 2 April 1, 2020 through March 31, 2021
MS07: High Pressure Injection Systems (IP Section 02.06) (2 Samples)
- (1) Unit 1 April 1, 2020 through March 31, 2021
- (2) Unit 2 April 1, 2020 through March 31, 2021
EP01: Drill/Exercise Performance (DEP) Sample (IP Section 02.12) (1 Sample)
- (1) October 1, 2020 through March 31, 2021 EP02: Emergency Response Organization (ERO) Drill Participation (IP Section 02.13) (1 Sample)
- (1) October 1, 2020 through March 31, 2021
EP03: Alert And Notification System (ANS) Reliability Sample (IP Section 02.14) (1 Sample)
- (1) October 1, 2020 through March 31, 2021
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in procedure use and adherence that might be indicative of a more significant safety issue.
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) CR-2021-00104, YELLOW Cornerstone in IST Program Scorecard for 2020-2 report period, specifically Cornerstone EQ-2, Adverse Trend/Equipment Performance on June 30,
INSPECTION RESULTS
Observation: Procedure use and Adherence Trend 71152 The inspectors evaluated a sample of NRC-identified issues that occurred over the first and second quarters of 2021. The inspectors identified a trend associated with human performance for procedure use and adherence, where individuals did not follow processes, procedures, and work instructions.
The inspectors evaluation did not reveal any new trends that could indicate a more significant safety issue, instead the inspectors evaluation identified a wider scope of applicability than previously identified by the licensee regarding the existing corrective actions regarding procedure use and adherence that led to multiple plant status control events. The inspectors identified the following performance deficiencies that were subsequently captured in the licensees corrective action program during routine inspection.
1. Inspectors identified that engineering heat exchanger inspection procedure 1/2-ADM-
2106.F01, Heat Exchanger Inspection Reports, documents the as found condition of the heat exchanger, including any debris that may impact the component function, system function or system health. Debris includes biologics, like clams and zebra mussel, are of particular interest and engineering is procedurally directed to generate a corbicula report regardless of the clams or zebra mussel condition. For Unit 1 recirculation spray heat exchanger D, 1-RS-E-1D, engineering inspection discovered evidence of shell fragments yet determined a corbicula report was not necessary, that is a departure from the procedure. For 1-RS-E-1D heat exchanger with as found shell fragments, the inspectors confirmed chemical control of biologics is adequate and the heat exchanger capacity is met with the as found biological debris. (CR2021-04558).
inspection for submerged or degraded cables was not being performed as written in 1/2MI-75-Manhole-1E, Inspection of Manholes for Water Induced Damage.
Specifically, the section regarding, Inspect cables for swellings, cuts, scrapes or gouges. Contact Electrical Maintenance Supervisor if any listed or other damages is found was not consistently understood and performed when the inspectors questioned the maintenance crew performing the inspection. The inspectors confirmed that the licensee re-inspected the safety-related cables within the applicable manholes in accordance with the procedure and did not identify concerns.
(CR2021-04692).
3. Inspectors identified that fire protection transient combustible permits are not posted
with staged material as required by 1/2-ADM-1906. Instead the global transient combustible permit was developed and available at the sitewide central location of the Work Execution Center. This practice is not identified in the procedure as an acceptable alternative nor was the licensee able to locate the compiled global transient combustible permits at the Work Execution Center upon request (CR2021-03186). The inspectors completed a review of the applicable global transient permits and did not identify concerns regarding the control of the affected transient combustibles.
4. Inspectors identified that hourly fire watches for global transient combustible permits
are required per 1/2-ADM-1906. The global transient combustible permit reviewed by inspectors stated no fire watch indicating a misalignment between the procedure and the permit. The inspectors confirmed that the required fire watches were performed in accordance with the procedure requirements (CR2021-05252).
5. Inspectors identified that transient combustible permits issued for the 1R27 auxiliary
building significantly underestimated the quantity of staged combustible material. The inspectors estimated staged material appeared bounded by the baseline/threshold fire risk evaluation established in Calculation No. B-084 (CR2021-05259).
The inspectors screened the performance deficiencies for significance in accordance with IMC 0612, Appendix B, Issue Screening and Appendix E, Examples of Minor Issues, and determined them to be minor. The licensee is evaluating this trend in the corrective action program, under CR2021-05656.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 29, 2021, the inspectors presented the Unit 1 ISI inspection results to Matthew Enos, General Plant Manager and other members of the licensee staff.
- On May 20, 2021, the inspectors presented the Radiation Inspection Exit/Debrief inspection results to William Cothen, Director of Performance Improvement and other members of the licensee staff.
- On June 10, 2021, the inspectors presented the Emergency Preparedness Program Inspection results to William Cothen, Director of Performance Improvement, and other members of the licensee staff.
- On July 21, 2021, the inspectors presented the integrated inspection results to John Grabnar and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
10080-RM-0411-
001
Valve Operator No Diagram Low/High Head Safety Injection
Revision 23
10080-RM-0413-
001
Recirculation Spray System
Revision 12
RM-0407-003
Valve Operator No. Diagram Chemical and Volume Control
System
Revision 26
(Figure No.
7-3)
RM-0411-001
Safety Injection System
Revision 31
RM-0413-002
Quench Spray System
Revision 21
Procedures
1OM-52.4.R.1.F
Station Shutdown From 100% Power to Mode 5
Revision 40
1OST-11.18
Low Head Safety Injection Pump Boric Acid Flow Path
Verification
Revision 13
2OST-13.2
Quench Spray Pump [2QSS*P21B] Test
Revision 38
Work Orders
200759653
Miscellaneous
1-ITS-1
Fire Drill Scenario
06/07/2021
Procedures
Pump
Pump Cubicles Fire Compartment 3-IS-,2,3,4
Revision 2
PCA Shop Fire Compartment 1-SB-GEN
Revision 3
Outage Central Fire Compartment 1-SB-GEN
Revision 2
Hot
Hot Lab & RP Offices Fire Compartment 1-SB-GEN
Revision 3
East
Turbine Building Basement East Fire Compartment 1-TB-1
Revision 3
West
Turbine Building Basement West Fire Compartment 1-TB-1
Revision 3
Turbine Mezzanine
Revision 3
Turbine Operating Deck
Revision 2
Corrective Action
Documents
21-02964
21-03925
21-3839
21-3848
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
21-3973
Corrective Action
Documents
Resulting from
Inspection
21-04080
CR2021-04692
Miscellaneous
8700-DMC-3111
735 PAB Flood Level Reanalysis for LER 1-95-010 Failure
03/23/2001
EM 30612
Evaluation of CCR Heat Exchanger RW Expansion Joints
2/15/1987
PRA-BV1-AL-R07 Beaver Valley Power Station, Unit 1, PRA Notebook, Internal
Flooding Analysis
Revision 7
TER 8323
Technical Evaluation Report to evaluate a gap width of up to
for sealing the charging pump flood plugs using detail
MC-1
Revision 0
Procedures
1OM-9.4.AAJ
Aux Bldg North Sump Level High
Revision 2
1OM-9.4.AAO
Aux Bldg South Sump Level High
Revision 1
Unit 1/Unit 2MI-
75-Manhole-1E
Inspection of Manholes for Water Induced Damage
Effective
2/27/2019
Work Orders
200783118
Corrective Action
Documents
21-03025
21-03541
Corrective Action
Documents
Resulting from
Inspection
21-04558
Miscellaneous
Heat Exchanger Inspection Report, 1RS-E-1C
05/20/2021
Heat Exchanger Inspection Report, 1RS-E-1D
05/20/2021
Beaver Valley Unit 1, River Water Projects Readiness
Review during 1R27
05/06/2021
Heat Exchanger Inspection Report, 1RS-E-1A
05/20/2021
Heat Exchanger Inspection Report, 1RS-E-1B
05/20/2021
Corrective Action
Documents
2019-08565
Insulation Fretting on Unit-1 Pressurizer 4 Spray Line
10/17/2019
2019-08793
Indication Reported on Weld SI-72-8-S01
10/23/2019
20-01101
Bergen-Patterson Snubber - Piston Seal Integrity Testing
Deficiency
2/12/2020
20-01487
Loss of communication to Unit 1 Safety Injection Line
2/26/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Temperature Monitoring Equipment
21-02779
1R27 Containment Exterior Deficiencies Identified by 1BVT-
1.47.1
04/11/2021
21-03181
Indications of Wear on Piping Upstream of 1RC-8 (Loop 1B
Sup to Sample Sys Isol)
04/21/2021
21-03271
1R27 Containment Liner Coating Deficiencies Identified
during the Performance of 1BVT 1.47.1
04/24/2021
Corrective Action
Documents
Resulting from
Inspection
21-03365
Wrong Figure Included in NDE UT Report
04/27/2021
Work Orders
200804178
Repair of 1QS-4
05/05/2021
200816800
SG 1C Upper Bergen Paterson Snubber piston seals
integrity test RC-HC-12C
200850354
Perform repairs (light surface conditioning) to 3/4"-RC-52-
1502-Q1 below valve 1RC-8 at the locations specified in
QC1-2021-0-102
05/03/2021
200850357
Install sheet metal sleeves for wear protections under the
joints of the insulation on lines RC-42, RC-52, RC-62 per
ECP 19-0206-00
04/30/2021
71111.11Q Miscellaneous
Simulator Guide
Station Blackout Unit 2, Lesson Plan Number G-OTLC-
2103S-BLACKOUT_BV2
Revision 0
Procedures
2OM-53A.1.ECA-
0.0(ISS3)
Loss of All Emergency 4KV AC Power
Revision 6
Corrective Action
Documents
2014-14551
21-03147
21-03784
21-03999
21-04085
Miscellaneous
Risk Management Plan associated with the work order
Risk Management
Plant
1R27 Critical, Battery BAT-1-5 Replacement
approved
03/12/2021
Procedures
1OST-24.9
Turbine Driven AFW Pump (1FW-P-2) Operability Test
Revision 61
Unit1/Unit2OM-
Purging Smoke or Toxic Gases from the Control Room
Revision 3
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
44A.4.P
Unit1/Unit2OM-
44A.4A.A
Post Control Room Habitability System Actuation/Recovery
Revision 17
Work Orders
200759653
200787095
200851666
Corrective Action
Documents
21-01889
21-03541
21-03577
21-03586
21-03626
21-04284
21-04326
21-04654
Drawings
0569C-001
Pressurizer Safety Valve, 6 in 1500 lb Inlet x 6 in 600 lb
Outlet
Revision D
8700-RE-21MK
ELEM DIAG VENTILATION SYS (VS) SH 10 OF 29 -
CONTROL ROOM SH 2 OF 4
Revision 10
8700-RE-21NK
ELEM DIAG VENTILATION SYS (VS) SH 33-CONT PNL
CONT UNIT CMPR VS-E-4B
Revision 4
RE-0021MJ
ELEM DIAG VENTILATION SYS (VS) SH 9 OF 29 -
CONTROL ROOM SH 1 OF 4
Revision 13
RE-0021NK
Elem Diag Vent Syst (VS) Control Panel Control Room Cond
Unit Cmpr VS-E-4B
Revision 0
RM-0430-001
Valve Oper No Diagram, Service Wtr Supply & Distribution
Revision 38
RM-0430-001
Valve Oper No Diagram, Service Water Primary Cooling
Revision 43
Miscellaneous
Follow-up Operability Determination for CR2021-01889
Intake Structure RW Inlet Temperature
from
10/20/2019
to 3/06/2021
8700-DMC-1548
Recirculation Spray Heat Exchanger Inputs for MAAP
Containment Analysis
dated
05/18/2012
Notification:
Engineering Evaluation Request
06/14/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
601322580
ODMI No BV1-
21-01
RV-1RC-551B, Pressurizer Safety Valve, Leakby at Low
RCS Pressure
Revision 0
Report 5733
Target Rock Model 0569C-001 Pressurizer Safety Valve
vendor tech manual
Revision E
Procedures
1OST-30.12A
Train 'A' Reactor Plant River Water System Full Flow Test
Revision 39
NOP-OP-1009
Operability Determinations and Functionality Assessments
Revision 9
Unit1/Unit2-ADM-
2019
Revision 18
Unit1/Unit2-ADM-
2039
Revision 18
Corrective Action
Documents
21-01945
21-02368
21-03926
Miscellaneous
AMS Report
Number
BV2010R0
Final Report of AMS Tests, Investigation of Beaver Valley
Unit 2 C Steam Generator Level Deviation Alarm
December
20
ECP-21-0051-001 Implementation documentation for ECP-21-0051
ODMI BV2-20-08
C Steam Generator Narrow Range Level Spikes
Revision 0
Corrective Action
Documents
21-03613
Miscellaneous
Onenote Chemistry Log
for May 4, 5
& 20, 2021
The emergent issues log
05/04/2021
Procedures
1/2 CMP-75-
Masoneilan-3M
Repair of Masoneilian 20000/21000 Series Control Valve
with Quick Change Trim
Revision 9
1/2-CMP-I-03-001
Repair and Replacement of Flux Mapping System
Components
Revision 11
1/2MI-75-
Packing-1M
Valve Packing Instruction
Revision 15
1OST-36.1
Diesel Generator No. 1 Monthly Test
Revision 72
Unit 1/Unit 2
CMP-75-
Expansion Joint-
Inspection and Replacement of Garlock Rubber Expansion
Joints
effective
04/12/2017
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
1M
Work Orders
200749129
200789184
200796175
200812767
200837181
Procedures
1OM-50.4.D1
Reactor Startup From Mode 3 to Mode 2-Initial Criticality
Revision 1
1OM-52.4.B
Load Following
Revision 60
1RST-2.1
Initial Approach to Criticality after Refueling
Revision 19
1RST-2.2
Core Design Check Test
Revision 21
Corrective Action
Documents
21-03071
21-03771
21-03774
21-03791
Procedures
1/2OST-76.15A
FLEX RCS Boration Pumps Operational Inspection and
Performance Test
Revision 1
1BVT 1.47.2
Containment Type 'A' Leak Test
Revision 8
1BVT 11.47.2
Unit 1 Containment Leakage Rate Testing Program
Revision 13
1OST-11.14A
LHSI Full Flow Test
Revision 36
1OST-11.14B
HHSI Full Flow Test
Revision 43
1OST-30.12A
Train 'A' Reactor Plant River Water System Full Flow Test
Revision 39
1OST-30.14A
Stroke Test of A RPRW Valves
Revision 6
1OST-47.177
Type 'B' Leak Test - Equipment Hatch
Revision 0
Work Orders
200788540
Miscellaneous
Beaver Valley Power Station Alert and Notification System
Design Report
04/21/2020
Miscellaneous
Beaver Valley Power Station, On-Shift Staffing Analysis
Revision 1
Corrective Action
Documents
Resulting from
Inspection
CR-2021-04512
CR-2021-04540
CR-2021-04541
Miscellaneous
Beaver Valley Emergency Preparedness Plan
Revision 11
Beaver Valley Power Station Evacuation Time Estimates
Revision 2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-2021-02839
Plant Operators entered a High Radiation are without
receiving a high radiation area brief
04/13/2021
Corrective Action
Documents
Resulting from
Inspection
CR-2021-03185
Briefing area noise level too high
04/21/2021
CR-2021-03187
Survey maps used for briefings not updated
04/21/2021
CR-2021-03631
No Telltale at Equipment Hatch to verify airflow into
Containment vs out of Containment
05/04/2021
Radiation Work
Permits (RWPs)
21-0506
Operations - Routine Functions
Revision 0
Corrective Action
Documents
20-01576
20-01629
20-03394
20-06076
20-06215
20-06659
20-06685
20-06875
20-07201
20-07389
20-07863
20-08448
Miscellaneous
Program Health
Scorecard
report period 2020-2
07/01/2020
to
2/31/2020