IR 05000334/2021010
| ML21272A232 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/29/2021 |
| From: | Glenn Dentel Division of Operating Reactors |
| To: | Grabnar J Energy Harbor Nuclear Corp |
| Dentel G | |
| References | |
| IR 2021010 | |
| Download: ML21272A232 (10) | |
Text
September 29, 2021
SUBJECT:
BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000334/2021010 AND 05000412/2021010
Dear Mr. Grabnar:
On September 16, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Beaver Valley Power Station, Units 1 and 2 and discussed the results of this inspection with Mr. Matthew Enos, General Plant Manager, Nuclear, 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, Glenn T. Dentel, Chief Engineering 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:
05000334/2021010 and 05000412/2021010
Enterprise Identifier: I-2021-010-0017
Licensee:
Energy Harbor Nuclear Corporation
Facility:
Beaver Valley Power Station, Units 1 and 2
Location:
Shippingport, PA 15077
Inspection Dates:
August 30, 2021 to September 16, 2021
Inspectors:
E. Dipaolo, Senior Reactor Inspector
L. Dumont, Reactor Inspector
D. Kern, Senior Reactor Inspector
Approved By:
Glenn T. Dentel, Chief
Engineering Branch 2
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a triennial fire protection 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 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.
However, all the inspection activities were performed onsite. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
===71111.21N.05 - Fire Protection Team Inspection (FPTI)
Structures, Systems, and Components (SSCs) Credited for Fire Prevention, Detection, Suppression, or Post-Fire Safe Shutdown Review (IP Section 03.01)===
The inspectors verified that the following systems credited in the approved fire protection program could perform their licensing basis function:
- (1) Fire Protection Water Supply System
- (2) Auxiliary Feedwater System
- (3) Chemical Volume Control System
- (4) Fire Barriers
Fire Protection Program Administrative Controls (IP Section 03.02) (2 Samples)
The inspectors verified that the selected fire protection administrative controls were implemented in accordance with the current licensing basis. The inspectors verified that the controls were properly implemented with adequate procedures and that the controls met committed industry standards. The following fire protection administrative controls were reviewed:
- (1) Control of Transient Combustible Material
- (2) National Fire Protection Association (NFPA) 805 Monitoring Program
Fire Protection Program Changes/Modifications (IP Section 03.03) (2 Samples)
The inspectors reviewed fire protection changes/modifications to ensure that they did not constitute an adverse effect on the ability to safely shutdown post-fire and did not degrade assumptions and performance capability stated in the in the safe shutdown analysis. The inspectors verified that fire protection program documents and procedures affected by the changes were updated. The following fire protections program changes/modifications were reviewed:
- (1) Engineering Change Package (ECP) 15-0450-000, Unit 1 Early Warning Fire Detection Initiating Device Replacement
- (2) ECP 18-0090-000 - Unit 2 Residual Heat Removal System Pump Breaker Normal System Alignment Change
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On September 16, 2021, the inspectors presented the triennial fire protection inspection results to Mr. Matthew Enos, General Plant Manager, Nuclear, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21N.05 Calculations
ARS-BV1-18-217
BVPS-1 Fire Protection SSD Recovery Action Report
ARS-BV2-18-219
BVPS-2 Fire Protection SSD Recovery Action Report
Calibration
Records
CR-2021-05522
Corrective Action
Documents
CR-2018-07052
CR-2018-08406
CR-2019-02500
CR-2019-05145
CR-2019-09822
CR-2020-00074
CR-2020-00079
CR-2020-07579
CR-2020-08721
CR-2021-00202
CR-2021-00578
CR-2021-00871
CR-2021-02372
CR-2021-03186
CR-2021-05523
Corrective Action
Documents
Resulting from
Inspection
CR-2021-06269
CR-2021-06588
CR-2021-06600
CR-2021-06615
CR-2021-06639
CR-2021-06645
CR-2021-06677
CR-2021-06683
CR-2021-06685
CR-2021-06686
CR-2021-06692
CR-2021-06837
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
CR-2021-06844
CR-2021-06868
CR-2021-06886
CR-2021-06906
CR-2021-06950
CR-2021-06954
CR-2021-06966
CR-2021-06973
Drawings
OP Manual
Figure No. 33-1
Fire Protection-Water
OP Manual
Figure No. 33-2
Fire Protection-Water
Engineering
Changes
ECP 18-0090-
000
Unit 2 Residual Heat Removal System Pump Breaker
Normal System Alignment Change
Engineering
Evaluations
10080-DMC-
0915
Beaver Valley Unit 1 and Unit 2 Fire Water Analysis
Engineering
Evaluation
Request
601155097
Fire Protection
Program Change
Evaluation
(FPPCE)15-025
NFPA 20 Code Compliance Review
FPPCE 15-026
Engineering Evaluation of Specified NFPA 24
Requirements
FPPCE 18-085
Unit 2 RHS Pump Breaker NSA Chan
FPPCE 21-019
Pre-NRC Fire Protection Inspection Self-Assessment-No
Surveillance Test that Document Sprinkler System
Inspections
FPPCE 21-021
Fire Alarm and Halon Discharge in Unit 1 Cable Tunnel 1-
CV-3
PRA-BV1-21-
001-R00
BVPS-1 Configuration Risk Determination for Both Normal
Fire Pumps Out of Service
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PRA-BV2-21-
2-R00
BVPS-2 Configuration Risk Determination for Both Normal
Fire Pumps Out of Service
Miscellaneous
Beaver Valley Power Station Unit 1 Updated Final Safety
Analysis Report
Beaver Valley Power Station Unit 2 Updated Final Safety
Analysis Report
Beaver Valley Power Station Units 1 and 2 Fire Safety
Analysis
Fire Protection Program Health Report, January-June
21
1/2OST-33.12
Fire Pump Flow Test
11/21/2019
and
06/23/2021
1OST-33.34
GDC Diesel Driven Fire Pump Operation Test
08/12/2021
1OST-33.7
Motor Driven Fire Pump Operation Test
03/26/2021
and
05/15/2021
1OST-33.8
Diesel Engine Driven Fire Pump Operation Test
07/17/2021
and
08/14/2021
2OM-10.3
Power Supply and Control Switch List
Procedures
1/2-ADM-1900
1/2-ADM-1906
Control of Transient Combustible and Flammable
Materials
1/2-ADM-1908
Fire Protection Performance Monitoring Program
1/2OM-56B.4A.E
Safe Shutdown Intent and Methodology
1OM-33.4.G
Motor-Driven Fire Pump
1OM-33.4.H
Engine-Driven Fire Pump
1OM-56B.4.CR1
Unit 1 Control Room Fire
1OM-56B.4.NS1
Unit 1 Normal Switchgear Room Fire
2OM-10.4.A
Residual Heat Removal System Startup
2OM-10.4.C
Residual Heat Removal System Shutdown
2OM-56B.4.CB1
Unit 2 Instrumentation and Relay Area
BVBP-OPS-0043
Control of Time Sensitive Actions
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
NOBP-OP-1113
Control of Time Sensitive Operator Actions
Self-
Assessments
ATA-2021-8471
Beaver Valley Power Station Pre-NRC Fire Prevention
Inspection Self-Assessment
08/20/2021
Work Orders
200531720
200531721
200531725
200531735
200713993
200713997
200715299
200715317
200716516
200716518