IR 05000334/2021012
| ML21083A102 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/24/2021 |
| From: | Matt Young NRC/RGN-I/DRP/PB5 |
| To: | Grabnar J Energy Harbor Nuclear Corp |
| Young M | |
| References | |
| IR 2021012 | |
| Download: ML21083A102 (14) | |
Text
March 24, 2021
SUBJECT:
BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - BIENNIAL PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000334/2021012 AND 05000412/2021012
Dear Mr. Grabnar:
On February 26, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Beaver Valley Power Station, Units 1 and 2 and 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.
The NRC inspection team reviewed the stations corrective action program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for corrective action programs. Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments.
Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment, and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews the team found no evidence of challenges to your organizations safety-conscious work environment.
Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
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, X /RA/
Signed by: Matthew R. Young
Matt R. Young, Chief Reactor Projects Branch 5 Division of Reactor Projects
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:
05000334/2021012 and 05000412/2021012
Enterprise Identifier: I-2021-012-0008
Licensee:
Energy Harbor Nuclear Corporation
Facility:
Beaver Valley Power Station, Units 1 and 2
Location:
Shippingport PA
Inspection Dates:
February 8, 2021 to February 26, 2021
Inspectors:
L. Cline, Senior Project Engineer
S. Monarque, Resident Inspector
R. Rolph, Resident Inspector
R. Vadella, Project Engineer
Approved By:
Matt R. Young, Chief
Reactor Projects Branch 5
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a biennial problem identification and resolution 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.
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), inspectors were directed to begin telework. In addition, regional baseline inspections were evaluated to determine if all or 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.
OTHER ACTIVITIES - BASELINE
71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 02.04)
- (1) The inspectors performed a biennial assessment of the licensees problem identification and resolution performance in the following areas:
- Corrective Action Program Effectiveness in problem identification, prioritization, evaluation, and corrective action, which also included a review of corrective actions for issues identified in the Unit 1 chemical volume control system, Unit 2 service water system, and the Unit 2 auxiliary feedwater system and aging management issues identified and evaluated in the last five years.
- Use of Operating Experience.
- Completed Self-Assessments and Audits.
- Health of the Safety Conscious Work Environment.
INSPECTION RESULTS
Assessment 71152B Corrective Action Program Effectiveness -
Problem Identification: The inspectors determined that, in general, the licensee identified issues and entered them into the corrective action program at a low threshold.
Problem Prioritization and Evaluation: Based on the samples reviewed, the inspectors determined that, in general, the licensee appropriately prioritized and evaluated issues commensurate with the safety significance of the identified problem. The licensee appropriately screened condition reports for operability and reportability, categorized condition reports by significance, and assigned actions to the appropriate department for evaluation and resolution. However, the inspectors identified one minor performance deficiency associated with condition report categorization/prioritization, that is documented in the applicable section below.
Corrective Actions: The inspectors determined that the overall corrective action program performance related to resolving problems was effective. In most cases, the licensee implemented corrective actions to resolve problems in a timely manner.
Assessment 71152B Use of Operating Experience -
The team determined that the licensee appropriately evaluated industry operating experience for its relevance to the facility. The licensee appropriately incorporated both internal and external operating experience into plant procedures and processes.
Self-Assessments and Audits -
The team reviewed a sample of self-assessments and audits to assess whether the licensee was identifying and addressing performance trends. The team concluded that the licensee had an effective self-assessment and audit process.
Assessment 71152B Safety-Conscious Work Environment -
The inspectors interviewed a total of 18 individuals using the questions included in Appendix A of Inspection Procedure 71152. The purpose of these interviews was to evaluate the willingness of licensee staff to raise nuclear safety issues and to evaluate the perceived effectiveness of the corrective action program at resolving identified problems. The personnel interviewed were selected from the Operations, Engineering, Maintenance, Security, and the Chemistry/Radiation Protection work groups. To supplement these discussions, the inspectors interviewed the Employee Concerns Program (ECP) representative and reviewed the ECP case log and selected case files. The inspectors also reviewed the licensee's programs for monitoring and maintaining a safety-conscious work environment. This included the results from the last employee safety-conscious work environment survey and the most recent semi-annual nuclear safety culture monitoring panel meetings and corrective actions to address the areas for improvement identified by these programs.
All individuals interviewed by the inspectors indicated that they would raise nuclear safety concerns. Most individuals felt that their management was receptive to receiving safety concerns and generally addressed them promptly, commensurate with the significance of the concern. All interviewees were aware of the licensee's ECP. Most stated they would use the program if necessary and were confident that their identify would be protected. All others were neutral on the use of the ECP. The inspectors shared the results of the inspectors' interviews of site staff with the site's ECP representative.
Minor Performance Deficiency 71152B Minor Performance Deficiency: The inspectors identified a minor performance deficiency associated with the Mitigating Systems cornerstone because the licensee did not categorize the condition described in CR-2020-0718 in accordance with guidance provided in licensee procedure NOP-LP-2001, Corrective Action Process. CR-2020-0718 documented that on September 16, 2020, NRC inspectors identified that the flood door between the A and B cubicles in the intake structure was open when it should have been shut (see NCV 05000334/2020004-01 and NCV 05000334/2020004-02). On October 21, 2020, after completing its evaluation of this condition, the licensee determined it had caused a loss of safety-related function for both trains of Unit 1 river water. Licensee procedure NOP-LP-2001, 1, provides a list of examples of significant conditions adverse to quality (SCAQs)to aid station management in determining proper categorization of identified conditions. The first example on that list of SCAQs is entry into unplanned standard Technical Specification Limiting Condition for Operation 3.0.3, or its equivalent, for the loss of safety-related function.
Contrary to this guidance, the licensee did not categorize the condition as an SCAQ. The licensee entered this condition into the corrective action program as CR-2021-01329.
Screening: The inspectors determined the performance deficiency was minor. In accordance with Inspection Manual Chapter 0612, Appendix B, more-than-minor screening questions, it did not adversely affect the Mitigating Systems cornerstone objective to ensure the availability, reliability, and capability of systems that respond to initiating events to prevent undesirable consequences. Adequate corrective actions were in progress to prevent recurrence of the loss of control of the service water cubicle flood door that was identified on September 16, 2020. Specifically, new signs were placed on the doors that clearly described the impact of leaving the doors open on the safety systems located in the affected rooms, the doors were locked, and the licensee had generated a long-term corrective action program action to track installation of permanent locks with unique keys that will be stored in the control room.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On February 26, 2021, the inspectors presented the biennial problem identification and resolution inspection results to Mr. John Grabnar, Site Vice President and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-2019-01357
(AA)
NRC Green Finding Fourth Quarter 2018 Unit 2 B
Safeguards Area Air Conditioning Unit
CR-2019-02895
(AA)
Missed ODCM (offsite dose calculation manual) surveillance
CR-2019-05844
(AA)
Question the effectiveness of a Beta scintillation detector
installed into a gamma detector well as a result of ECP 18-
0043
CR-2019-06200
(AA)
NRC Baseline Inspection 2019-410: Site Protection:
Operations: NRC observed Main Gate Search
CR-2019-08565
(AA)
Aging - Insulation Fretting on Unit-1 Pressurizer 4" Spray
Line
CR-2019-08793
(AA)
Indication Reported on Weld SI-72-8-S01
CR-2019-08793
(AA)
Aging - Indication Reported on Weld SI-72-8-S01
CR-2020-02845
(AR)
Cale came free from drum of Unit 2 Fuel Elevator (2FNT-
EL21)
CR-2020-02857
(AA)
Validity of sample results from Unit 1 gas waste surge tank
CR-2020-05481
(AA)
1CT-P-1A (Cooling Tower Pump 1A) Lower Motor Guide
Bearing Failure
CR-2020-06889
(AA)
NRC Baseline Inspection 2020: Site Protection: Operations:
NRC Observed Main Gate Search
CR-2020-07218
(AA)
20 DBAI flood door BV-1IS05-11 (A to B intake cubicle
crosstie flood door) found open during DBAI walkdown
CR-2020-08313
(NC)
Personal Injury Occurred During Main Intake Bay Cleaning -
CRs
CR-2007-20026, CR-2013-10409, CR-2016-02973, CR-
2016-11890, CR-2017-05550, CR-2017-10960, CR-2018-
09111, CR-2019-00991, CR-2019-01259, CR-2019-01260,
CR-2019-01267, CR-2019-01319, CR-2019-01326, CR-
2019-01327, CR-2019-01329, CR-2019-01342, CR-2019-
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
01357, CR-2019-01436, CR-2019-01849, CR-2019-02006,
CR-2019-02105, CR-2019-02312, CR-2019-02597, CR-
2019-02598, CR-2019-02857, CR-2019-02895, CR-2019-
2948, CR-2019-03037, CR-2019-03133, CR-2019-03414,
CR-2019-03591, CR-2019-03723, CR-2019-03817, CR-
2019-03949, CR-2019-04071, CR-2019-04414, CR-2019-
04781, CR-2019-04815, CR-2019-04884, CR-2019-05522,
CR-2019-05844, CR-2019-05973, CR-2019-07576, CR-
2019-07583, CR-2019-07601, CR-2019-07663, CR-2019-
08133, CR-2019-08565, CR-2019-08565, CR-2019-08595,
CR-2019-08596, CR-2019-08793, CR-2019-08793, CR-
2019-08919, CR-2019-09938, CR-2019-10253, CR-2019-
10455, CR-2019-10621, CR-2019-12089, CR-2020-00580,
CR-2020-01436, CR-2020-02101, CR-2020-02168, CR-
20-02857, CR-2020-03333, CR-2020-03418, CR-2020-
03509, CR-2020-03575, CR-2020-03619, CR-2020-03936,
CR-2020-03949, CR-2020-03964, CR-2020-04953, CR-
20-05330, CR-2020-05557, CR-2020-05557, CR-2020-
05846, CR-2020-06003, CR-2020-06213, CR-2020-06214,
CR-2020-06215, CR-2020-06497, CR-2020-06498, CR-
20-06567, CR-2020-06659, CR-2020-06838, CR-2020-
06919, CR-2020-06928, CR-2020-07218, CR-2020-07218,
CR-2020-07389, CR-2020-07509, CR-2020-07622, CR-
20-07622, CR-2020-07881, CR-2020-08194, CR-2020-
261, CR-2020-08313, CR-2020-08354, CR-2020-08739,
CR-2020-08800, CR-2020-09081, CR-2020-09366, CR-
20-09398, CR-2020-09468, CR-2020-09578, CR-2021-
00137, CR-2021-00349, CR-2021-00375, CR-2021-00501,
CR-2021-00613, CR-2021-00985
Corrective Action
Documents
Resulting from
Inspection
CR 2021-01126, CR 2021-01191, CR 2021-01326, CR 2021-
01327, CR 2021-01329
Engineering
Changes
ECP-08-0496-
007
Temporary modification for Clamping 3 way valve HCV-1CH-
244 in position to isolate from Volume Control Tank for
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Repair of 1CH-11
ECP-08-0496-
008
Removal of Temporary Modification for Clamping 3 way
valve HCV-1CH-244 in Position to Isolate from Volume
Control Tank for Repair of 1CH-11
Engineering
Evaluations
OE-2019-0122
IN1901, Inadequate Evaluation of Temporary Alterations
OE-2019-0238
June 3, 2019 NRC INFORMATION NOTICE 2019-02:
EMERGENCY DIESEL GENERATOR EXCITATION
SYSTEM DIODE FAILURES
OE-2019-0240
IN1903, Inadequate Implementation of Clearance Processes
Results in Configuration Control Issues
OE-2019-0290
August 26, 2019 NRC INFORMATION NOTICE 2019-05:
POTENTIAL OVER-PRESSURIZATION OF HIGH
SPECIFIC-ACTIVITY ALPHA-EMITTING RADIOACTIVITY
SOURCES
OE-2019-0363
October 8, 2019 NRC INFORMATION NOTICE 2019-08:
FLOW-ACCELERATED CORROSION EVENTS
OE-2020-0272
IN 20-02, Flex Diesel Generator Operational Challenges
OE-2020-0375
IN20-03, Recall of Mechanical Rate of Rise and Fixed-
Temperature Heat Detectors
Miscellaneous
Beaver Valley SCWE Survey Results for September 2020
October
20
Beaver Valley
Unit 1 System
Health Report
20-2
System - 07 - Unit 1 Chemical and Volume Control System
2/01/2021
Beaver Valley
Unit 2 System
Health Report
20-2
System - 24B - Unit 2 Auxiliary Feedwater System
2/01/2021
Beaver Valley
Unit 2 System
Health Report
20-2
System - 30 - Unit 2 Service Water System
2/01/2021
FORM 1/2-ADM-
Heat Exchanger Inspection Report (2EGS-E21B - 2R21)
04/23/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2106.F01, Rev. 6
FORM 1/2-ADM-
2106.F01, Rev. 6
Heat Exchanger Inspection Report (2EGS-E22B - 2R21)
04/14/2020
FORM 1/2-ADM-
2106.F01, Rev. 6
Heat Exchanger Inspection Report (2EGS-E21A - 2R21)
04/23/2020
FORM 1/2-ADM-
2106.F01, Rev. 6
Heat Exchanger Inspection Report (2EGS-E22A - 2R21)
04/23/2020
Procedures
1/2-ENV-05.04
Radioactive Discharge Authorization - Liquid
Revision 4
1/2-PMP-M-30-
2
New Traveling Water Screen Inspection
Revision 2
1/2OST-30.21A
Beaver Valley Power Station Unit 1/2 Group 1 Flood Door
Seal System Operability Check
Revision 12
1/2OST-30.21B
Beaver Valley Unit 1/2 Group 2 Flood Door Seal System
Operability Check
Revision 12
10M-30.2A
Beaver Valley Power Station Unit 1 Precautions and
Limitations
Revision 13
20M-30.2.A
Beaver Valley Power Station Unit 2 Precautions and
Limitations
Revision 13
2OST-30.13A
Train A Service Water System Full Flow Test
Revision 48
2OST-30.13B
Train B Service Water System Full Flow Test
Revision 47
2OST-30.3
Service Water Pump [2SWS*P21B] Test
Revision 53
2OST-30.6B
Service Water Pump [2SWS*P21C] Test on Train B Header
Revision 36
BV-1OST-07-05
1CH-P-1B Centrifugal Charging Pump Operational Test
Quarterly
04/15/2019
BV-1OST-07-06
1CH-P-1C Centrifugal Charging Pump Operational Test
01/31/2020
BV-1OST-47-124
Type C leak Test Penetration Number 28
10/18/2019
NOBP-LP-20011
Cause Analysis
Revision 27
NOBP-LP-2008
Corrective Action Review Board
Revision 25
NOBP-LP-2100
Operating Experience Process
Revision 21
NOBP-LP-2501
Safety Culture Assessment
Revision 19
NOBP-LP-2502
Safety Culture Monitoring
Revision 14
NOP-ER-2001
Boric Acid Corrosion Control Program
2/27/2020
NOP-ER-2001
Boric Acid Corrosion Control Program
2/27/2020
NOP-LP-2001
Corrective Action Program
Revision 48
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NOP-OP-1004
Reactivity Management
Revision 17
NOP-OP-1004
Reactivity Event Classification
Revision 3
NORM-LP-2003
Analytical Methods Guidebook
Revision 13
Self-Assessments PA-BV-2019-
0001-005
Control of Transient Combustibles and Flammable Materials
03/14/2019
PA-BV-2019-
0001-006
Equipment Tagged in the Control Room
03/28/2019
PA-BV-2019-
25-013
Assessment of the pre job Brief for the Reactor Vessel Head
Installation, October 26, 2019
10/26/2019
PA-BV-2020-
0040-002
Resolution of Safety Relief and Valve Issues
PA-BV-2020-
0063-005
Adherence to Conduct of Operations Standards
08/21/2020
SA-2020-8414
71130.02 access control (2020)
SA-BN-2018-
298
Pre-PI&R 2019 NRC Inspection Assessment
2/18/2019
SA-BN-2019-
26
Unannounced quarterly ERO call In Drill -2019 Second
Quarter
Work Orders
WO 200520844, WO 200631412, WO 200635176, WO 200635813, WO 200635813, WO 200651457, WO 200673444, WO 200682247, WO 200685128, WO 200685129, WO 200694986, WO 200696791, WO 200696791, WO 200699695, WO 200699904, WO 200701456, WO 200701456, WO 200704682, WO 200709497, WO 200725699, WO 200737447, WO 200742874, WO 200744641, WO 200745425, WO 200756444, WO 200759434, WO 200759623, WO 200761676, WO 200761676, WO 200761677, WO 200761677, WO 200764217, WO 200764408, WO 200768652, WO 200771131, WO 200780726, WO 200780726, WO 200780726, WO 200781041, WO 200781851, WO 200783636, WO 200783637, WO 200783640, WO 200783641, WO 200788338, WO 200803106, WO 200803118, WO 200808349, WO 200820987, WO 200820999, WO 200821115, WO
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
200821883, WO 200826408, WO 200833299, WO 200841279, WO 200841286, WO 200841286, WO 200841306, WO 200841306