IR 05000354/2021010
| ML21259A194 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  (NPF-057) |
| Issue date: | 09/16/2021 |
| From: | Mel Gray Division of Operating Reactors |
| To: | Carr E Public Service Enterprise Group |
| Gray M | |
| References | |
| IR 2021010 | |
| Download: ML21259A194 (12) | |
Text
September 16, 2021
SUBJECT:
HOPE CREEK NUCLEAR GENERATING STATION - DESIGN BASES ASSURANCE INSPECTION (TEAMS) INSPECTION REPORT 05000354/2021010
Dear Mr. Carr:
On August 19, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Hope Creek Nuclear Generating Station and discussed the results of this inspection with Mr. Steven Poorman, Plant Manager 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, Mel Gray, Chief Engineering Branch 1 Division of Operating Reactor Safety
Docket No. 05000354 License No. NPF-57
Enclosure:
As stated
Inspection Report
Docket Number:
05000354
License Number:
Report Number:
Enterprise Identifier: I-2021-010-0023
Licensee:
Facility:
Hope Creek Nuclear Generating Station
Location:
Hancock's Bridge, New Jersey
Inspection Dates:
August 1, 2021, to August 19, 2021
Inspectors:
J. Ayala, Health Physicist
T. Corcoran, Project Engineer
J. Kulp, Senior Reactor Inspector
K. Mangan, Senior Reactor Inspector
N. Mentzer, Reactor Inspector
J. Schoppy, Senior Reactor Inspector
Approved By:
Mel Gray, Chief
Engineering Branch 1
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a design bases assurance inspection (teams) inspection at Hope Creek Nuclear Generating Station, 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. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
===71111.21M - Design Bases Assurance Inspection (Teams)
The inspectors evaluated the following components and listed applicable attributes, permanent modifications, and operating experience:
Design Review - Risk-Significant/Low Design Margin Components (IP Section 02.02)
=
- (1) D Service Water Pump and Strainer
- Material condition and installed configuration (e.g., visual inspection/walkdown)
- Normal, abnormal, and emergency operating procedures
- Consistency among design and licensing bases and other documents/procedures
- System health report, maintenance effectiveness and records, and corrective action history
- Equipment/environmental controls and qualification
- Design calculations
- Surveillance testing and recent test results
- System and component level performance monitoring
- Equipment protection from fire, flood, and water intrusion or spray
The team used Appendix B guidance for Valves, Pumps, Instrumentation, and As-Built System.
- (2) C Emergency Diesel Generator (Mechanical)
- Material condition and installed configuration (e.g., visual inspection/walkdown)
- Normal, abnormal, and emergency operating procedures
- Consistency among design and licensing bases and other documents/procedures
- System health report, maintenance effectiveness and records, and corrective action history
- Design calculations
- Surveillance testing and recent test results
- Environmental conditions
- Equipment protection from fire, flood, and water intrusion or spray
- Heat removal cooling water and ventilation
The team used Appendix B guidance for Valves, Pumps, Instrumentation, and As-Built System.
- (3) A Emergency Diesel Generator (Electrical) and A 4 KV Bus
- Material condition and installed configuration (e.g., visual inspection/walkdown)
- Normal, abnormal, and emergency operating procedures
- Consistency among design and licensing bases and other documents/procedures
- System health report, maintenance effectiveness and records, and corrective action history
- Control logic
- Design calculations
- Surveillance testing and recent test results
- Environmental conditions
- Contactor and fuse ratings; Component adequacy for minimum voltage
The team used Appendix B guidance for Instrumentation, Circuit Breakers and Fuses, Cables, Electric Loads, and As-Built System.
- (4) A 125 Vdc Battery and Bus
- Material condition and installed configuration (e.g., visual inspection/walkdown)
- Normal, abnormal, and emergency operating procedures
- Consistency among design and licensing bases and other documents/procedures
- System health report, maintenance effectiveness and records, and corrective action history
- Operator actions
- Design calculations
- Surveillance testing and recent test results
- Verify that component degradation is monitored
The team used Appendix B guidance for Valves, Instrumentation, and As-Built System.
Design Review - Large Early Release Frequency (LERFs) (IP Section 02.02) (1 Sample)
- (1) Risk Significant Operator Action: Vent Containment
- Material condition and installed configuration (e.g., visual inspection/walkdown)
- Normal, abnormal, and emergency operating procedures
- Consistency among design and licensing bases and other documents and procedures
- System health report, maintenance effectiveness and records, and corrective action history
- Operator actions
- Design calculations
- Surveillance testing and recent test results
- Equipment protection from fire, flood, and water intrusion or spray
The team used Appendix B guidance for Valves, Instrumentation, and As-Built System.
Modification Review - Permanent Mods (IP Section 02.03) (5 Samples)
- (1) Determine Maximum Pressure Difference across Residual Heat Removal Valve H1BC-BC-HV-F003B (80122981)
- (2) High Pressure Core Injection (HPCI) Turbine Supply and Exhaust Valve Replacement (80120777)
- (3) Removal of N2 Pressure and Floating Roofs from STACS Accumulators (80103199)
- (4) Hope Creek Power Range Nuclear Monitor (PRNM) Cable Installation (80111348)
- (5) DCC - Replace Hope Creek Reactor Recirculation Pump Motor M-G Set with Siemens Variable Frequency Drive (VFD) (80115139)
Review of Operating Experience Issues (IP Section 02.06) (3 Samples)
- (1) NRC Information Notice 2019-01: Inadequate Evaluation of Temporary Alterations
- (2) NRC Information Notice 2020-02: Flex Diesel Generator Operational Challenges
- (3) NRC Information Notice 2019-08: Flow-Accelerated Corrosion Events
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On August 19, 2021, the inspectors presented the design bases assurance inspection (teams) inspection results to Mr. Steven Poorman, Plant Manager and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71111.21M Calculation
E-15.16
Hope Creek FLEX Electrical System Loading Analysis
Revision 1
E-17D
Hope Creek Generating Station 125 VDC: Voltage Drop from
Distribution Panel to Load
Revision 6
E-4.1(Q)
HC Class 1E 125 VDC Station Battery & Charger Sizing
Revision 20
E-7.4
Class 1E 4.16 KV System Protective Relay Settings
Revision 0
E-7.6
Diesel Generator Protective Relaying
Revision 0
EA-0001
Station Service Water System Hydraulic Model
Revision 3
EA-0003
Station Service Water System Hydraulic Analysis
Revision 12
EG-0047
HCGS Ultimate Heat Sink Temperature Limits - EPU
Revision 0
M-55-1
High Pressure Coolant Injection
Revision 40
M-56-1
HPCI Pump Turbine
Revision 34
Corrective Action
Documents
20342072
20595574
20597337
20619795
20665278
20746839
20748532
20799788
20803684
20820758
20824624
20831232
20835513
20836925
20841318
20841966
20842484
20843007
20858724
20879324
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
20880246
20881375
20881971
20882031
20882345
20882386
20882476
20882477
Corrective Action
Documents
Resulting from
Inspection
20881918
20882155
20882156
20882158
20882161
20882162
20882163
20882167
20882168
20882169
20882195
20882201
20882215
20882356
20882357
20882358
20882374
20882375
20882376
20882418
20882420
20882457
20882475
20882494
20882495
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
20882498
20882499
20882516
20882536
20882677
20882708
20882727
20882740
20882747
20882769
20882771
20882772
20882809
20882821
20882829
20882830
20882831
20882833
20882866
20882876
20882947
20882986
20882990
Drawings
E-0006-2, Sheet
Single Line Meter & Relay Diagram 4.16 KV Class 1E Power
System
Revision 15
Engineering
Changes
80120777
Replacement of HPCI Steam Admission Valve H1FD-FD-
HV-F001
Revision 1
80122981
Maximum Pressure Difference Across Valve H1BC-BC-HV-
F003B
Revision 0
Engineering
Evaluations
207037
Evaluation of NRC Information Notice 2019-01
1/15/20
80111348
Hope Creek PRNM Cable Installation
Revision 0
TE 70210392-
0010
Fire Watch Change for EDG & DFOST Room CO2 Systems
in Manual Operation
11/22/19
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Safety Evaluation by the Office of Nuclear Reactor
Regulation Related to Amendment No. 59 to Facility
Operating License No. NPF-57 Public Service Electric & Gas
Company Atlantic City Electric Company Hope Creek
Generating Station (ML20058K164)
11/22/93
18055-P-0501
Line Index for the Hope Creek Generating Station
Revision 39
2800 (010)
Hope Creek RRP VFD, Commissioning Documents
Revision 2
2800 (012)
Hope Creek RRP VFD, S7-400, FPC Cabinet
Revision 2
H-1-BJXX-MSE-
0438-0 Status
Code 52
Safety Evaluation: Overpressurization of the HPCI Discharge
Lines Hope Creek Generating Station
dated
8/18/86
HC.MD-PM.PB-
0001
4.16 KV Breaker Cleaning and PM
10/24/19
HC.OP-IS.BJ-
0001
HPCI Main and Booster Pump Set - OP204 and OP217 -
Inservice Test
dated 6/9/21
HC.OP-ISEA-
0004
Service Water Pump -DP502 - Inservice Test
dated 6/8/21
HC.OP-ST.KJ-
0005
Integrated Emergency Diesel Generator 1AG400 Test
11/19/19
Common Cause Failure of Boiling-Water Reactor
Recirculation Pumps with Variable Speed Drives
dated
9/10/10
Malfunctions of Emergency Diesel Generator Speed Switch
Circuits
dated
11/1/10
Ineffective Use of Vendor Technical Recommendations
dated
4/24/12
PE109Q-013
4KV Switchgear
Revision 19
PM018Q-0499-
003
Revision 38
Procedures
Plant Barrier Control Program
Revision 6
Diesel Fuel Oil
Storage and
Transfer System
Operation
Emergency Diesel Generator Operation
Revision 78
Conduct of Flow Accelerated Corrosion Activities
Revision 9
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Guidelines for Flow Accelerated Corrosion Activities
Revision 11
Actions for Inoperable Fire Protection - Hope Creek Station
Revision 7
HC.OP-EO.ZZ-
0318
Containment Venting
Revision 14
HC.OP-IS.BJ-
0001
HPCI Main and Booster Pump Set - OP204 and OP217 -
Inservice Test
Revision 71
HC.OP-SO.EG-
0001
Safety and Turbine Auxiliaries Cooling Water System
Operation
Revision 57
HC.OP-SO.JE-
0001
Diesel Fuel Oil Storage and Transfer System Operation
Revision 34
Work Orders
30156952
30179604
264387
264387
286640
30323052
30324962
30325063
30334179
30341497
30342467
60096929
60097059
60097061
60135941
60150262